Details of the Researcher

PHOTO

Yuji Hatano
Section
Graduate School of Engineering
Job title
Professor
Degree
  • 博士(工学)(九州大学)

e-Rad No.
80218487
Researcher ID

Research History 5

  • 2024/07 - Present
    Tohoku University Department of Quantum Science and Energy Engineering, Graduate School of Engineering Professor

  • 2019/10 - 2024/06
    University of Toyama Faculty of Science, Academic Assembly Professor

  • 2005/04 - 2019/09
    University of Toyama Hydrogen Isotope Research Center Professor

  • 1998/04 - 2005/03
    University of Toyama Hydrogen Isotope Research Center

  • 1989/07 - 1998/03
    Kyushu University Department of Nuclear Engineering, Faculty of Engineering Assistant Professor

Education 2

  • Kyushu University Graduate School of Engineering Department of Nuclear Engineering

    1989/04 - 1989/06

  • Kyushu University Faculty of Engineering Department of Nuclear Engineering

    1985/04 - 1989/03

Committee Memberships 10

  • 一般社団法人 日本原子力学会 核融合工学部会副部会長

    2019/04 - 2021/03

  • 一般社団法人 プラズマ・核融合学会 理事

    2014/06 - 2017/06

  • 内閣府 フュージョンエネルギーの実現に向けた安全確保の基本的な考え方検討タスクフォース

    2024/04 - Present

  • National Institute for Quantum Science and Technology Project Committee Member, International Fusion Energy Research Center

    2023/09 - Present

  • International Workshop on Hydrogen Isotopes in Fusion Reactor Materials International Program Committee

    2017/04 - Present

  • International Symposium on Tritium Science and Technology International Steering Committee

    2017/04 - Present

  • International Conference on Fusion Reactor Materials International Advisory Committee

    2017/04 - Present

  • Japan-China Symposium on Materials for Advanced Energy System and Fission & Fusion Engineering Organizing Committee

    2016/09 - Present

  • Asia-Pacific Symposium on Tritium Science International Program Committee

    2015/11 - Present

  • 一般社団法人日本原子力学会 核融合工学部会部会長

    2021/04 - 2023/03

Show all ︎Show first 5

Professional Memberships 8

  • American Nuclear Society

    2020 - Present

  • 日本アイソトープ協会

  • プラズマ・核融合学会

  • 日本金属学会

  • 日本原子力学会

  • Japan Society of Plasma Sience and Nuclear Fusion Research

  • Japan Institute of Metals

  • Atomic Energy Society of Japan

︎Show all ︎Show first 5

Research Interests 5

  • 水素

  • トリチウム

  • 核融合

  • エネルギー材料

  • Materials Science for Energy Conversion

Research Areas 4

  • Nanotechnology/Materials / Energy chemistry /

  • Energy / Nuclear engineering /

  • Energy / Nuclear fusion /

  • Nanotechnology/Materials / Structural and functional materials /

Awards 5

  1. Top Reviewer Awards, Nuclear Fusion

    2022/12 IOP Publishing

  2. Technical Development Award

    2020/12 The Japan Society of Plasma Science and Nuclear Fusion Research

  3. Best Reviewer Award, Journal of Nuclear Materials

    2014/12 Elsevier

  4. 日本原子力学会奨励賞

    1999

  5. Award for Young Researcher, Atomic Energy Society of Japan

    1999

Papers 278

  1. Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry Peer-reviewed

    S. E. Lee, Y. Hatano, M. Hara, S. Masuzaki, M. Tokitani, M. Oyaizu, H. Kurotaki, D. Hamaguchi, H. Nakamura, N. Asakura, Y. Oya, J. Likonen, A. Widdowson, S. Jachmich, K. Helariutta, M. Rubel

    Fusion Engineering and Design 160 2020/11

    DOI: 10.1016/j.fusengdes.2020.111959  

    ISSN: 0920-3796

  2. D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation Peer-reviewed

    Y. Oya, F. Sun, Y. Yamauchi, Y. Nobuta, M. Shimada, C. N. Taylor, W. R. Wampler, M. Nakata, L. M. Garrison, Y. Hatano

    Journal of Nuclear Materials 539 2020/10

    DOI: 10.1016/j.jnucmat.2020.152323  

    ISSN: 0022-3115

  3. Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing Peer-reviewed

    V. Kh Alimov, Y. Hatano, T. Kuwabara, T. Toyama, Y. Someya, A. V. Spitsyn

    Nuclear Fusion 60 (9) 2020/09

    DOI: 10.1088/1741-4326/aba337  

    ISSN: 0029-5515

    eISSN: 1741-4326

  4. Kinetics of deuterium penetration into neutron-irradiated tungsten under exposure to high flux deuterium plasma Peer-reviewed

    M. Yajima, Y. Hatano, N. Ohno, T. Kuwabara, T. Toyama, M. Takagi, K. Suzuki

    Nuclear Materials and Energy 21 2019/12

    DOI: 10.1016/j.nme.2019.100699  

    eISSN: 2352-1791

  5. Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign Peer-reviewed

    Y. Hatano, S. E. Lee, J. Likonen, S. Koivuranta, M. Hara, S. Masuzaki, N. Asakura, K. Isobe, T. Hayashi, J. Ikonen, A. Widdowson, X. Litaudon, S. Abduallev, M. Abhangi, P. Abreu, M. Afzal, K. M. Aggarwal, T. Ahlgren, J. H. Ahn, L. Aho-Mantila, N. Aiba, M. Airila, R. Albanese, V. Aldred, D. Alegre, E. Alessi, P. Aleynikov, A. Alfier, A. Alkseev, M. Allinson, B. Alper, E. Alves, G. Ambrosino, R. Ambrosino, L. Amicucci, V. Amosov, E. Andersson Sunden, M. Angelone, M. Anghel, C. Angioni, L. Appel, C. Appelbee, P. Arena, M. Ariola, H. Arnichand, S. Arshad, A. Ash, N. Ashikawa, V. Aslanyan, O. Asunta, F. Auriemma, Y. Austin, L. Avotina, M. D. Axton, C. Ayres, M. Bacharis, A. Baciero, D. Baiao, S. Bailey, A. Baker, I. Balboa, M. Balden, N. Balshaw, R. Bament, J. W. Banks, Y. F. Baranov, M. A. Barnard, D. Barnes, M. Barnes, R. Barnsley, A. Baron Wiechec, L. Barrera Orte, M. Baruzzo, V. Basiuk, M. Bassan, R. Bastow, A. Batista, P. Batistoni, R. Baughan, B. Bauvir, L. Baylor, B. Bazylev, J. Beal, P. S. Beaumont, M. Beckers, B. Beckett, A. Becoulet, N. Bekris, M. Beldishevski, K. Bell, F. Belli, M. Bellinger, E. Belonohy, N. Ben Ayed, N. A. Benterman, H. Bergasker, J. Bernardo, M. Bernert, M. Berry, L. Bertalot

    Nuclear Materials and Energy 18 258-261 2019/01/01

    DOI: 10.1016/j.nme.2019.01.001  

    eISSN: 2352-1791

  6. Tritium retention characteristics in dust particles in JET with ITER-like wall Peer-reviewed

    T. Otsuka, S. Masuzaki, N. Ashikawa, Y. Hatano, Y. Asakura, Tatsuya Suzuki, Takumi Suzuki, K. Isobe, T. Hayashi, M. Tokitani, Y. Oya, D. Hamaguchi, H. Kurotaki, R. Sakamoto, Hiroyasu Tanigawa, M. Nakamichi, A. Widdowson, M. Rubel

    Nuclear Materials and Energy 17 279-283 2018/12

    DOI: 10.1016/j.nme.2018.11.001  

    eISSN: 2352-1791

  7. Deuterium retention in neutron-irradiated single-crystal tungsten Peer-reviewed

    M. Shimada, Y. Oya, W. R. Wampler, Y. Yamauchi, C. N. Taylor, L. M. Garrison, D. A. Buchenauer, Y. Hatano

    Fusion Engineering and Design 136 1161-1167 2018/11

    DOI: 10.1016/j.fusengdes.2018.04.094  

    ISSN: 0920-3796

  8. Surface morphology of F82H steel exposed to low-energy D plasma at elevated temperatures Peer-reviewed

    V. Kh Alimov, Y. Hatano, N. Yoshida, N. P. Bobyr, M. Oyaidzu, M. Tokitani, T. Hayashi

    Journal of Nuclear Materials 510 366-372 2018/11

    DOI: 10.1016/j.jnucmat.2018.08.037  

    ISSN: 0022-3115

  9. Deuterium trapping at vacancy clusters in electron/neutron-irradiated tungsten studied by positron annihilation spectroscopy Peer-reviewed

    T. Toyama, K. Ami, K. Inoue, Y. Nagai, K. Sato, Q. Xu, Y. Hatano

    Journal of Nuclear Materials 499 464-470 2018/02

    DOI: 10.1016/j.jnucmat.2017.11.022  

    ISSN: 0022-3115

  10. Surface modification and sputtering erosion of iron and copper exposed to low-energy, high-flux deuterium plasmas seeded with metal species Peer-reviewed

    V. Kh Alimov, Y. Hatano, M. Balden, M. Oyaizu, K. Isobe, H. Nakamura, T. Hayashi

    Nuclear Materials and Energy 13 81-89 2017/12

    DOI: 10.1016/j.nme.2017.06.003  

    eISSN: 2352-1791

  11. Progress in the U.S./Japan PHENIX project for the technological assessment of plasma facing components for DEMO reactors Peer-reviewed

    Yutai Katoh, Daniel Clark, Yoshio Ueda, Yuji Hatano, Minami Yoda, Adrian S. Sabau, Takehiko Yokomine, Lauren M. Garrison, J. Wilna Geringer, Akira Hasegawa, Tatsuya Hinoki, Masashi Shimada, Dean Buchenauer, Yasuhisa Oya, Takeo Muroga

    Fusion Science and Technology 72 (3) 222-232 2017/10

    DOI: 10.1080/15361055.2017.1333868  

    ISSN: 1536-1055

  12. Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions: Effects of irradiation temperature Peer-reviewed

    Y. Hatano, K. Ami, V. Kh Alimov

    Nuclear Materials and Energy 9 93-97 2016/12/01

    DOI: 10.1016/j.nme.2016.06.016  

    eISSN: 2352-1791

  13. Permeation and permeation barrier Peer-reviewed

    Yuji Hatano

    Tritium: Fuel of Fusion Reactors 207-229 2016/01/01

    DOI: 10.1007/978-4-431-56460-7_9  

  14. Surface modification and deuterium retention in reduced activation ferritic martensitic steels exposed to low-energy, high flux D plasma and D<inf>2</inf> gas Peer-reviewed

    V. Kh Alimov, Y. Hatano, K. Sugiyama, M. Balden, T. Höschen, M. Oyaidzu, J. Roth, J. Dorner, M. Fußeder, T. Yamanishi

    Physica Scripta T159 2014

    DOI: 10.1088/0031-8949/2014/T159/014049  

    ISSN: 0281-1847

  15. Deuterium trapping at defects created with neutron and ion irradiations in tungsten Peer-reviewed

    Y. Hatano, M. Shimada, T. Otsuka, Y. Oya, V. Kh Alimov, M. Hara, J. Shi, M. Kobayashi, T. Oda, G. Cao, K. Okuno, T. Tanaka, K. Sugiyama, J. Roth, B. Tyburska-Püschel, J. Dorner, N. Yoshida, N. Futagami, H. Watanabe, M. Hatakeyama, H. Kurishita, M. Sokolov, Y. Katoh

    Nuclear Fusion 53 (7) 2013/07

    DOI: 10.1088/0029-5515/53/7/073006  

    ISSN: 0029-5515

    eISSN: 1741-4326

  16. Trapping of hydrogen isotopes in radiation defects formed in tungsten by neutron and ion irradiations Peer-reviewed

    Y. Hatano, M. Shimada, V. Kh Alimov, J. Shi, M. Hara, T. Nozaki, Y. Oya, M. Kobayashi, K. Okuno, T. Oda, G. Cao, N. Yoshida, N. Futagami, K. Sugiyama, J. Roth, B. Tyburska-Püschel, J. Dorner, I. Takagi, M. Hatakeyama, H. Kurishita, M. A. Sokolov

    Journal of Nuclear Materials 438 (SUPPL) 2013

    DOI: 10.1016/j.jnucmat.2013.01.018  

    ISSN: 0022-3115

  17. Retention of hydrogen isotopes in neutron irradiated tungsten

    Yuji Hatano, Masashi Shimada, Yasuhisa Oya, Guoping Cao, Makoto Kobayashi, Masanori Hara, Brad J. Merrill, Kenji Okuno, Mikhail A. Sokolov, Yutai Katoh

    Materials Transactions 54 (4) 437-441 2013

    DOI: 10.2320/matertrans.MG201204  

    ISSN: 1345-9678

    eISSN: 1347-5320

  18. Helium bubble behaviour in W-Mo alloys by in-situ TEM under He+ irradiation

    Joshua Ashley, Mitsutaka Miyamoto, Yuji Hatano, Enrique Jimenez-Melero

    Journal of Nuclear Materials 2025/07

    DOI: 10.1016/j.jnucmat.2025.156017  

  19. Simultaneous exposure to neutron radiation and hydrogen environment: Effect on hydrogen retention

    Weicheng Zhong, Yuji Hatano, Takaaki Koyanagi, Adrian M. Schrell, Yutai Katoh

    International Journal of Hydrogen Energy 2025/07

    DOI: 10.1016/j.ijhydene.2025.06.138  

  20. Tritium permeation through Inconel 600 under high temperature, high pressure water environment: Influence of oxidation of coexisting materials and gas addition

    Azusa Matsumoto, Yuji Hatano

    Fusion Engineering and Design 214 114896-114896 2025/05

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2025.114896  

    ISSN: 0920-3796

  21. Scrape-off layer and divertor physics: Chapter 5 of the special issue: on the path to tokamak burning plasma operation

    K. Krieger, S. Brezinsek, J.W. Coenen, H. Frerichs, A. Kallenbach, A.W. Leonard, T. Loarer, S. Ratynskaia, N. Vianello, N. Asakura, M. Bernert, D. Carralero, R. Ding, D. Douai, T. Eich, Y. Gasparyan, A. Hakola, Y. Hatano, M. Jakubowski, M. Kobayashi, S. Krasheninnikov, S. Masuzaki, T. Nakano, R. Neu, R.A. Pitts, J. Rapp, K. Schmid, O. Schmitz, D. Tskhakaya, L. Wang, T. Wauters, S. Wiesen

    Nuclear Fusion 65 (4) 043001-043001 2025/03/10

    Publisher: IOP Publishing

    DOI: 10.1088/1741-4326/adaf42  

    ISSN: 0029-5515

    eISSN: 1741-4326

    More details Close

    Abstract Since the publication of the review Progress in the ITER Physics Basis (PIPB) in 2007, significant progress has been made in understanding the processes at the plasma-material interface. This review, part of the ITPA Nuclear Fusion Special Issue On the Path to Burning Plasma Operation, presents these developments, focusing on key areas such as the physics of plasma exhaust, plasma-material interactions, and the properties of plasma-facing materials and their evolution under plasma exposure. The coordinated efforts of the ITPA Topical Group on Scrape-Off Layer and Divertor Physics (DivSOL) have been instrumental in identifying and addressing critical research and development issues in numerous collaborative experimental and modelling projects.

  22. Effects of neutron irradiation on hydrogen isotope permeation on W-Re

    Yuzuka Hoshino, Fei Sun, Makoto I. Kobayashi, Takeshi Toyama, Robert Kolasinski, Chase N. Taylor, Masashi Shimada, Yuji Hatano, Yasuhisa Oya

    Fusion Engineering and Design 211 114769-114769 2025/02

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2024.114769  

    ISSN: 0920-3796

  23. Comparative characterization of mixed spectra and thermal neutron shielded irradiated tungsten

    Hanns Gietl, Chase N. Taylor, Yuji Hatano, Yasuhisa Oya, Masashi Shimada

    Journal of Nuclear Materials 2025/01

    DOI: 10.1016/j.jnucmat.2024.155498  

  24. Precise Spectroscopy of the 3⁢𝑛 and 3⁢𝑝 Systems via the 3H⁡(𝑡,3He)⁢3⁢𝑛 and 3He⁢(3He,𝑡)⁢3⁢𝑝 Reactions at Intermediate Energies Peer-reviewed

    K. Miki, K. Kameya, D. Sakai, R. Urayama, N. Imai, S. Ishikawa, S. Michimasa, S. Ota, M. Sasano, H. Takeda, T. Uesaka, H. Haba, M. Hara, Y. Hatano, T. Hayamizu, N. Kobayashi, A. Tamii, S. Adachi, T. Chillery, M. Dozono, Y. Fujikawa, H. Fujita, N. Fukuda, T. Furuno, J. Gao, S. Goto, S. Hanai, S. Hayakawa, Y. Hijikata, K. Himi, Y. Hirai, J. W. Hwang, M. Ichimura, D. Inomoto, M. Inoue, H. Kasahara, T. Kawabata, K. Kishimoto, S. Kitayama, K. Kusaka, J. Li, Y. Maeda, Y. Maruta, T. Matsui, T. Matsuzaki, S. Nakai, H. Nishibata, M. Otake, Y. Saito, H. Sakai, A. Sakaue, H. Sato, K. Sekiguchi, Y. Shimizu, S. Shimoura, L. Stuhl, T. Sumikama, H. Suzuki, R. Tsuji, S. Tsuji, H. Umetsu, Y. Utsuki, T. Wakasa, A. Watanabe, K. Yako, Y. Yanagisawa, N. Yokota, C. Yonemura, K. Yoshida, M. Yoshimoto

    Physical Review Letters 133 (1) 2024/07/03

    Publisher: American Physical Society (APS)

    DOI: 10.1103/physrevlett.133.012501  

    ISSN: 0031-9007

    eISSN: 1079-7114

  25. Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures Peer-reviewed

    Masayuki Tokitani, Mitsutaka Miyamoto, Suguru Masuzaki, Yuji Hatano, Sun Eui Lee, Yasuhisa Oya, Hironori Kurotaki, Nobuyuki Asakura, Hirofumi Nakamura, Takumi Hayashi, Marek Rubel, Anna Widdowson, Jari Likonen

    Nuclear Materials and Energy 39 101678-101678 2024/06

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2024.101678  

    ISSN: 2352-1791

  26. Liquid metal compatibility of pre-oxidized FeCrAl in flowing Sn Peer-reviewed

    B.A. Pint, Y.F. Su, M. Romedenne, J. Jun, M. Kondo, N. Oono, K. Sakamoto, Yuji Hatano

    Fusion Engineering and Design 2024/05

    DOI: 10.1016/j.fusengdes.2024.114377  

  27. Evaluation of hydrogen embrittlement in ODS-Cu, Cu–Cr–Zr, and Cu–Cr alloys using slow strain rate technique test Peer-reviewed

    M. Hatakeyama, Y. Asai, D. Nakato, M. Nishimura, Y. Hatano, S. Sunada, K. Sato

    Nuclear Materials and Energy 38 101580-101580 2024/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2024.101580  

    ISSN: 2352-1791

  28. Visualization of Hydrogen and Hydrogen-induced Defects in Tensile-deformed Pure Iron Using Hydrogen Microprint and Tritium Autoradiography Peer-reviewed

    Toshiaki Manaka, Goroh Itoh, Junya Kobayashi, Shigeru Kuramoto, Yuji Hatano

    ISIJ International 64 (4) 655-659 2024/02/28

    Publisher: Iron and Steel Institute of Japan

    DOI: 10.2355/isijinternational.isijint-2023-279  

    ISSN: 0915-1559

    eISSN: 1347-5460

  29. Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall Peer-reviewed

    Y. Torikai, G. Kikuchi, A. Owada, S. Masuzaki, T. Otsuka, N. Ashikawa, M. Yajima, M. Tokitani, Y. Oya, S.E. Lee, Y. Hatano, N. Asakura, T. Hayashi, M. Oyaidzu, J. Likonen, A. Widdowson, M. Rubel

    Nuclear Fusion 64 (1) 016032-016032 2023/12/05

    Publisher: IOP Publishing

    DOI: 10.1088/1741-4326/ad0c08  

    ISSN: 0029-5515

    eISSN: 1741-4326

    More details Close

    Abstract Divertor tiles after Joint European Torus-ITER like wall (JET-ILW) campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and areal tritium activities, poloidal tritium distribution in the divertor and the presence of that isotope in individual dust particles. In the divertor tiles, the majority of tritium is detected in the surface region and, the areal activities in the ILW divertor are in the 0.5–12 kBq cm−2 range. The activity in the ILW dust is associated mainly with the presence of carbon particles being a legacy from the JET-C operation. The total tritium activities show significant differences between the JET operation with ILW and the earlier phase with the carbon wall (JET-C) indicating that tritium retention has been significantly decreased in the operation with ILW.

  30. Development and fabrication of a thick Ti-3H target for the 3H(t,3He)3n experiment at intermediate energies Peer-reviewed

    K. Miki, Y. Utsuki, M. Hara, Y. Hatano, N. Imai, M. Inoue, M. Itoh, K. Kameya, S. Kitayama, Y. Maruta, Y. Matsuda, Y. Saito, D. Sakai, T. Uesaka, H. Umetsu, R. Urayama, J. Wang, K. Kamada, Y. Shoji, A. Yoshikawa

    Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 2023/11

    DOI: 10.1016/j.nima.2023.168583  

  31. Thermal annealing effect on D retention for damaged W-10%Re alloy Peer-reviewed

    Yasuhisa Oya, Nao Inozume, Yuzuka Hoshino, Naoaki Yoshida, Tatsuya Hinoki, Kiyohiro Yabuuchi, Yuji Hatano, Qilai Zhou, Fei Sun, Robert Kolasinski, Chase N. Taylor, Masashi Shimada

    Fusion Engineering and Design 196 113981-113981 2023/11

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2023.113981  

    ISSN: 0920-3796

  32. Ultrahigh-Flux Concerting Materials Peer-reviewed

    Takuya NAGASAKA, Makoto I. KOBAYASHI, Teruya TANAKA, Sadatsugu TAKAYAMA, Hiroyuki NOTO, Jingjie SHEN, Tatsuya HINOKI, Kiyohiro YABUUCHI, Katsuaki TANABE, Ryuta KASADA, Sosuke KONDO, Shuhei NOGAMI, Hiroki KURITA, Naoyuki HASHIMOTO, Yuji YAMAUCHI, Yasuhisa OYA, Takumi CHIKADA, Yuji HATANO, Kazunari KATAYAMA, Makoto OYA, Naoko OONO, Yoshitaka MORI

    Plasma and Fusion Research 18 2505085-2505085 2023/10/23

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.18.2505085  

    eISSN: 1880-6821

  33. Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure Peer-reviewed

    Yasuhisa Oya, Kyosuke Ashizawa, Fei Sun, Shiori Hirata, Naoko Ashikawa, Yoji Someya, Yuji Hatano, Robert Kolasinski, Chase N. Taylor, Masashi Shimada

    Fusion Engineering and Design 194 113722-113722 2023/09

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2023.113722  

    ISSN: 0920-3796

  34. Control and Application of Ultrahigh Hydrogen Flux in Materials Peer-reviewed

    Makoto I. KOBAYASHI, Yuji HATANO, Masanori HARA, Yasuhisa OYA, Yuji YAMAUCHI, Teppei OTSUKA, Takuya NAGASAKA

    Plasma and Fusion Research 18 2105073-2105073 2023/08/17

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.18.2105073  

    eISSN: 1880-6821

  35. Deuterium retention in reduced activation ferritic/martensitic steel EUROFER97 exposed to low-energy deuterium plasma Peer-reviewed

    V.Kh. Alimov, J. Roth, K. Sugiyama, M.J. Baldwin, R.P. Doerner, Y. Hatano

    Nuclear Materials and Energy 35 101430-101430 2023/06

    Publisher: Elsevier {BV}

    DOI: 10.1016/j.nme.2023.101430  

    ISSN: 2352-1791

  36. Irradiation effects on binary tungsten alloys at elevated temperatures: Vacancy cluster formation, precipitation of alloying elements and irradiation hardening Peer-reviewed

    Jing Wang, Yuji Hatano, Takeshi Toyama, Tatsuya Hinoki, Kiyohiro Yabuuchi, Yi-fan Zhang, Bing Ma, Alexander V. Spitsyn, Nikolay P. Bobyr, Koji Inoue, Yasuyoshi Nagai

    Materials &amp; Design 229 111899-111899 2023/05

    Publisher: Elsevier BV

    DOI: 10.1016/j.matdes.2023.111899  

    ISSN: 0264-1275

  37. Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments Peer-reviewed

    S. Lee, Y. Hatano, S. Masuzaki, Y. Oya, M. Tokitani, M. Yajima, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, H. Kurotaki, T. Hayashi, T. Nozawa, A.M. Ito, J. Likonen, A. Widdowson, M. Rubel

    Nuclear Fusion 63 (4) 046023-046023 2023/03/08

    Publisher: IOP Publishing

    DOI: 10.1088/1741-4326/acb9a5  

    ISSN: 0029-5515

    eISSN: 1741-4326

    More details Close

    Abstract Tritium retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall (ILW) during the first (ILW1), third (ILW3) and all three (ILW1-3) campaigns were examined and evaluated. Tritium was deposited on the surfaces inside the castellation grooves together with deuterium, beryllium, oxygen, carbon and small amounts of metallic impurities such as nickel, copper and tungsten. The tritium content after the ILW1 campaign was greater than after the ILW3 campaign. This is attributed to the steadily decreasing amount of carbon impurities in JET from campaign to campaign. The majority of tritium was retained in shallow regions in the grooves, up to 2 mm from the entrance to the gap. It was comparable on all sides of the castellation, i.e. no difference has been detected between the toroidal and poloidal gaps. Secondly, the tritium retention in the gaps was similar on all specimens independent of their position in the tokamak, while the retention on the plasma-facing surfaces clearly depended on the tile position. The tritium deposition patterns in the castellation were also compared with the deuterium distribution determined in earlier studies.

  38. Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment☆ Peer-reviewed

    Chase N. Taylor, Masashi Shimada, Yuji Nobuta, Makoto I. Kobayashi, Yasuhisa Oya, Yuji Hatano, Takaaki Koyanagi

    Nuclear Materials and Energy 34 101323-101323 2023/03

    Publisher: Elsevier {BV}

    DOI: 10.1016/j.nme.2022.101323  

    ISSN: 2352-1791

  39. Measurement of DNA length on video of fluorescence microscope by pix2pix trained by molecular dynamics simulation Peer-reviewed

    Seiki Saito, Ayumi Kobashi, Haruto Miura, Hiroaki Nakamura, Takahiro Kenmotsu, Yasuhisa Oya, Yuji Hatano

    Journal of Advanced Simulation in Science and Engineering 10 (1) 172-181 2023

    Publisher: Japan Society for Simulation Technology

    DOI: 10.15748/jasse.10.172  

    eISSN: 2188-5303

  40. Refractive index measurements of solid deuterium–tritium Peer-reviewed

    Keisuke Iwano, Jiaqi Zhang, Akifumi Iwamoto, Yuki Iwasa, Keisuke Shigemori, Masanori Hara, Yuji Hatano, Takayoshi Norimatsu, Kohei Yamanoi

    Scientific Reports 12 (1) 2022/12

    Publisher: Springer Science and Business Media LLC

    DOI: 10.1038/s41598-022-06298-1  

    eISSN: 2045-2322

    More details Close

    <title>Abstract</title>Physical properties of tritium (T) and deuterium (D) have been of great interest as a fuel for nuclear fusion. However, several kinds of the physical properties in a cryogenic environment have not been reported. Optical properties in liquid and solid phases are indispensable for the quality control of the DT fuel. We study the dependence of the refractive index of solid DT on temperature. A dedicated cryogenic system has been developed and forms a transparent solid DT in a prism cell. Refractive index measurements based on Snell’s law were conducted. The refractive indexes of solid DT are from 1.1618 ± 0.0002 to 1.1628 ± 0.0002 in the temperature range of 19.40 K to 17.89 K.

  41. Effect of rhenium addition on deuterium retention in neutron-irradiated tungsten Peer-reviewed

    Y. Nobuta, T. Toyama, A. Matsumoto, M. Shimada, Y. Oya, K. Inoue, Y. Nagai, Y. Hatano

    Journal of Nuclear Materials 566 2022/08/01

    DOI: 10.1016/j.jnucmat.2022.153774  

    ISSN: 0022-3115

  42. Neutron irradiation of tungsten in hydrogen environment at HFIR Peer-reviewed

    Nesrin O. Cetiner, Yuji Hatano, Joel L. McDuffee, Dan Ilas, Yutai Katoh, Josina W. Geringer, Takeshi Toyama

    Fusion Engineering and Design 178 113089-113089 2022/05

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2022.113089  

    ISSN: 0920-3796

  43. An overview of tritium retention in dust particles from the JET-ILW divertor Peer-reviewed

    T Otsuka, S Masuzaki, N Ashikawa, Y Torikai, Y Hatano, M Tokitani, Y Oya, N Asakura, T Hayashi, H Tanigawa, Y Iwai, A Widdowson, M Rubel

    Physica Scripta 97 (2) 024008-024008 2022/02/01

    Publisher: IOP Publishing

    DOI: 10.1088/1402-4896/ac445b  

    ISSN: 0031-8949

    eISSN: 1402-4896

    More details Close

    <title>Abstract</title> Tritium (T) retention characteristics in dust collected from the divertor in JET with ITER-like wall (JET-ILW) after the third campaign in 2015–2016 (ILW-3) have been examined in individual dust particles by combining radiography (tritium imaging plate technique) and electron probe micro-analysis. The results are summarized and compared with the data obtained after the first campaign in 2011–2012 (ILW-1). The dominant component in ILW-1 dust was carbon (C) originating from tungsten-coated carbon fibre composite (CFC) tiles in JET-ILW divertor and/or legacy of C dust after the JET operation with carbon wall. Around 85% of the total tritium retention in ILW-1 dust was attributed to the C dust. The retention in tungsten (W) and beryllium (Be) dominated particles was 100 times smaller than the highest T retention in carbon-based particles. After ILW-3 the main component contributing to the T retention was W. The number of small W particles with T increased, in comparison to ILW-1, most probably by the exfoliation and fragmentation of W coatings on CFC tiles though T retention in individual W particles was smaller than in C particles. The detection of only very few Be-dominated dust particles found after ILW-1 and ILW-3 could imply stable Be deposits on the divertor tiles.

  44. Suppression of vacancy formation and hydrogen isotope retention in irradiated tungsten by addition of chromium

    Jing Wang, Yuji Hatano, Takeshi Toyama, Tomoaki Suzudo, Tatsuya Hinoki, Vladimir Kh Alimov, Thomas Schwarz-Selinger

    Journal of Nuclear Materials 559 2022/02

    DOI: 10.1016/j.jnucmat.2021.153449  

    ISSN: 0022-3115

  45. Damages of DNA in tritiated water

    Yuji Hatano, Hiroaki Nakamura, Susumu Fujiwara, Seiki Saito, Takahiro Kenmotsu

    DNA Damage and Double Strand Breaks - Part A 131-152 2022

    Publisher: Elsevier

    DOI: 10.1016/bs.enz.2022.08.009  

    ISSN: 1874-6047

  46. Rate of double strand breaks of genome-sized DNA in tritiated water: Its dependence on tritium concentration and water temperature Peer-reviewed

    Yuji Hatano, Hiroto Shimoyachi, Tatsuya Asano, Takahiro Kenmotsu, Takuro Wada, Yasuhisa Oya, Hiroaki Nakamura, Susumu Fujiwara

    Journal of Advanced Simulation in Science and Engineering 9 (1) 198-205 2022/01

    Publisher: Japan Society for Simulation Technology

    DOI: 10.15748/jasse.9.198  

    eISSN: 2188-5303

  47. Microstructure, hardening and deuterium retention in CVD tungsten irradiated with neutrons at temperatures of defect recovery stages II and III

    Xiao Ou Yi, Tatsuya Kuwabara, Vladimir Kh Alimov, Yu Feng Du, Wen Tuo Han, Ping Ping Liu, Bin You Yan, Jiu Peng Song, Kenta Yoshida, Takeshi Toyama, Fa Rong Wan, Somei Ohnuki, Yuji Hatano, Yasuyoshi Nagai

    Tungsten 4 (3) 248-260 2022

    DOI: 10.1007/s42864-022-00161-6  

    ISSN: 2661-8028

    eISSN: 2661-8036

  48. Cracking behavior and microstructural, mechanical and thermal characteristics of tungsten–rhenium binary alloys fabricated by laser powder bed fusion

    Takafumi Yamamoto, Masanori Hara, Yuji Hatano

    International Journal of Refractory Metals and Hard Materials 100 2021/11/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.ijrmhm.2021.105651  

    ISSN: 2213-3917 0263-4368

  49. Protective behavior of tea catechins against DNA double strand breaks produced by radiations with different linear energy transfer

    Takuro Wada, Ayaka Koike, Shota Yamazaki, Kyosuke Ashizawa, Fei Sun, Yuji Hatano, Hiroto Shimoyachi, Takahiro Kenmotsu, Takashi Ikka, Yasuhisa Oya

    Fusion Engineering and Design 172 2021/11/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.fusengdes.2021.112700  

    ISSN: 0920-3796

  50. Tritium behavior in isotropic graphite at room temperature

    Naritoshi Kawamura, Shiro Matoba, Shunsuke Makimura, Masanori Hara, Yuji Hatano

    Fusion Engineering and Design 172 112801-112801 2021/11

    Publisher: Elsevier {BV}

    DOI: 10.1016/j.fusengdes.2021.112801  

    ISSN: 0920-3796

  51. Penetration of deuterium into neutron-irradiated tungsten under plasma exposure

    Miyuki Yajima, Yuji Hatano, Vladimir Alimov, Takeshi Toyama, Tatsuya Kuwabara, Thomas Schwarz-Selinger, Yasuhisa Oya, Alexander Spitsyn, Noriyasu Ohno

    Physica Scripta 2021/10/01

    Publisher: IOP Publishing

    DOI: 10.1088/1402-4896/ac2c20  

    ISSN: 0031-8949

    eISSN: 1402-4896

  52. Effects of irradiation temperature on tritium retention in stainless steel type 316L

    Masao Matsuyama, Hideki Zushi, Kazuaki Hanada, Yasuhisa Oya, Yuji Hatano

    Fusion Engineering and Design 169 2021/08/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.fusengdes.2021.112436  

    ISSN: 0920-3796

  53. Effect of temperature distribution on tritium permeation rate to cooling water in JA DEMO condition

    Kazunari Katayama, Youji Someya, Takumi Chikada, Kenji Tobita, Hirofumi Nakamura, Yuji Hatano, Ryoji Hiwatari, Yoshiteru Sakamoto, Akito Ipponsugi, Makoto Oya

    Fusion Engineering and Design 169 112576-112576 2021/08

    Publisher: Elsevier BV

    DOI: 10.1016/j.fusengdes.2021.112576  

    ISSN: 0920-3796

  54. Numerical analysis of deuterium migration behaviors in tungsten damaged by fast neutron by means of gas absorption method

    Makoto Kobayashi, Masashi Shimada, Chase N. Taylor, Yuji Nobuta, Yuji Hatano, Yasuhisa Oya

    FUSION ENGINEERING AND DESIGN 168 2021/07

    DOI: 10.1016/j.fusengdes.2021.112635  

    ISSN: 0920-3796

    eISSN: 1873-7196

  55. Erratum: “Conceptual Design of HFIR Irradiation Experiment for Material Compatibility Study on Liquid Sn Divertor” [Plasma Fusion Res. 16, 2405040 (2021)] Peer-reviewed

    Masatoshi KONDO, Bruce A. PINT, Jiheon JUN, Nick RUSSELL, Joel McDUFFEE, Masafumi AKIYOSHI, Teruya TANAKA, Naoko OONO, Junichi MIYAZAWA, Josina, W GERINGER, Yutai KATOH, Yuji HATANO

    Plasma and Fusion Research 16 (0) 2905088-2905088 2021/06/02

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.16.2905088  

    ISSN: 1880-6821

  56. Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature

    M. Oya, M. Shimada, C. N. Taylor, M. Kobayashi, Y. Nobuta, Y. Yamauchi, Y. Oya, Y. Ueda, Y. Hatano

    NUCLEAR MATERIALS AND ENERGY 27 2021/06

    DOI: 10.1016/j.nme.2021.100980  

    eISSN: 2352-1791

  57. Global distribution of tritium in JET with the ITER-like wall

    S. E. Lee, Y. Hatano, M. Tokitani, S. Masuzaki, Y. Oya, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, K. Isobe, H. Kurotaki, D. Hamaguchi, T. Hayashi, A. Widdowson, S. Jachmich, J. Likonen, M. Rubel

    Nuclear Materials and Energy 26 2021/03

    DOI: 10.1016/j.nme.2021.100930  

    ISSN: 2352-1791

    eISSN: 2352-1791

  58. Deuterium retention in W and binary W alloys irradiated with high energy Fe ions

    Jing Wang, Yuji Hatano, Tatsuya Hinoki, Vladimir Kh. Alimov, Alexander V. Spitsyn, Nikolay P. Bobyr, Sosuke Kondo, Takeshi Toyama, Heun Tae Lee, Yoshio Ueda, Thomas Schwarz-Selinger

    JOURNAL OF NUCLEAR MATERIALS 545 2021/03

    DOI: 10.1016/j.jnucmat.2020.152749  

    ISSN: 0022-3115

    eISSN: 1873-4820

  59. Effects of fabrication conditions on the microstructure, pore characteristics and gas retention of pure tungsten prepared by laser powder bed fusion

    Takafumi Yamamoto, Masanori Hara, Yuji Hatano

    International Journal of Refractory Metals and Hard Materials 95 2021/02/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.ijrmhm.2020.105410  

    ISSN: 2213-3917 0263-4368

  60. Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures

    Alimov, V.K., Torikai, Y., Hatano, Y., Schwarz-Selinger, T.

    Fusion Engineering and Design 162 2021

    DOI: 10.1016/j.fusengdes.2020.112100  

    ISSN: 0920-3796

  61. Image processing method for automatic measurement of number of DNA breaks

    Seiki Saito, Hiroaki Nakamura, Takahiro Kenmotsu, Yasuhisa Oya, Yuji Hatano, Yuichi Tamura, Susumu Fujiwara, Hiroaki Ohtani

    Journal of Advanced Simulation in Science and Engineering 8 (2) 173-193 2021

    Publisher: Japan Society for Simulation Technology

    DOI: 10.15748/jasse.8.173  

    eISSN: 2188-5303

  62. Effects of Helium Seeding on Deuterium Retention in Neutron-Irradiated Tungsten

    Yuji Nobuta, Masashi Shimada, Chase N. Taylor, Yasuhisa Oya, Yuji Hatano, Yaqiao Wu, Megha Dubey

    FUSION SCIENCE AND TECHNOLOGY 77 (1) 76-79 2021/01

    DOI: 10.1080/15361055.2020.1843314  

    ISSN: 1536-1055

    eISSN: 1943-7641

  63. Evaluation of the hydrogen solubility and diffusivity in proton-conducting oxides by converting the PSL values of a tritium imaging plate

    M. Khalid Hossain, Kenichi Hashizume, Yuji Hatano

    Nuclear Materials and Energy 25 2020/12/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.nme.2020.100875  

    ISSN: 2352-1791

  64. Dynamics of Hydrogen Isotope Absorption and Emission of Neutron-Irradiated Tungsten

    Takeshi Toyama, Miyuki Yajima, Noriyasu Ohno, Tatsuya Kuwabara, Vladimir Kh Alimov, Yuji Hatano

    PLASMA AND FUSION RESEARCH 15 2020/11

    DOI: 10.1585/pfr.15.1505081  

    ISSN: 1880-6821

  65. Gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and ceramic coatings Peer-reviewed

    Shota Nakazawa, Kazuki Nakamura, Hikari Fujita, Hans Maier, Thomas Schwarz-Selinger, Yuji Hatano, Naoko Ashikawa, Wataru Inami, Yoshimasa Kawata, Takumi Chikada

    Journal of Nuclear Materials 539 2020/10

    DOI: 10.1016/j.jnucmat.2020.152321  

    ISSN: 0022-3115

  66. Hydrogen isotope exchange in tungsten during heating in hydrogen isotope gas atmosphere Peer-reviewed

    Yuji Nobuta, Yuji Hatano, Sun Eui Lee, Masato Nakayama

    Fusion Engineering and Design 157 111703-111703 2020/08

    Publisher: Elsevier {BV}

    DOI: 10.1016/j.fusengdes.2020.111703  

    ISSN: 0920-3796

  67. Development of Tritium Tracer Doped Liquid Fuel Target for Inertial Confinement Fusion at the Gekko XII-LFEX Facility Peer-reviewed

    Yasunobu Arikawa, Yuki Iwasa, Kohei Yamanoi, Keisuke Iwano, Shinsuke Fujioka, Akifumi Iwamoto, Mitsuo Nakai, Yuji Hatano, Masanori Hara, Satoshi Akamaru, Takayoshi Norimatsu, Ryosuke Kodama

    Fusion Science and Technology 76 (4) 464-470 2020/05/18

    DOI: 10.1080/15361055.2020.1716458  

    ISSN: 1536-1055

    eISSN: 1943-7641

  68. Hydrogen Isotope Dissolution and Release Behavior of Rare Earth Oxides Peer-reviewed

    M. Khalid Hossain, Kenichi Hashizume, Shinnosuke Jo, Kaname Kawaguchi, Yuji Hatano

    Fusion Science and Technology 76 (4) 553-566 2020/05/18

    DOI: 10.1080/15361055.2020.1728173  

    ISSN: 1536-1055

    eISSN: 1943-7641

  69. Influence of Internal Structure of Semiconductor Detector on Spectrum of X-Rays Induced by Tritium Beta Rays Peer-reviewed

    S. E. Lee, Y. Hatano, M. Hara, M. Matsuyama

    Fusion Science and Technology 76 (3) 327-332 2020/04

    DOI: 10.1080/15361055.2020.1711855  

    ISSN: 1536-1055

    eISSN: 1943-7641

  70. Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method Peer-reviewed

    Mingzhong Zhao, Moeko Nakata, Fei Sun, Yuji Hatano, Yoji Someya, Kenji Tobita, Yasuhisa Oya

    Fusion Science and Technology 76 (3) 246-251 2020/04

    DOI: 10.1080/15361055.2019.1705727  

    ISSN: 1536-1055

    eISSN: 1943-7641

  71. Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H<inf>2</inf>+ at high temperature Peer-reviewed

    Qilai Zhou, Akihiro Togari, Moeko Nakata, Mingzhong Zhao, Fei Sun, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Masanori Hara, Yuji Hatano, Yasuhisa Oya

    International Journal of Hydrogen Energy 45 (16) 9959-9968 2020/03/20

    DOI: 10.1016/j.ijhydene.2020.01.202  

    ISSN: 0360-3199

  72. Surface morphology of the bulk tungsten divertor tiles from JET ITER-like wall Peer-reviewed

    J. E.T. Contributors, M. Tokitani, M. Miyamoto, S. Masuzaki, Y. Hatano, S. E. Lee, Y. Oya, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, T. Hayashi, N. Asakura, A. Widdowson, S. Jachmich, M. Rubel

    Physica Scripta 2020 (T171) 2020/01/01

    DOI: 10.1088/1402-4896/ab3d09  

    ISSN: 0031-8949

    eISSN: 1402-4896

  73. Determination of retained tritium from ILW dust particles in JET Peer-reviewed

    N. Ashikawa, Y. Torikai, N. Asakura, T. Otsuka, A. Widdowson, M. Rubel, M. Oyaizu, M. Hara, S. Masuzaki, K. Isobe, Y. Hatano, K. Heinola, A. Baron-Wiechec, S. Jachmich, T. Hayashi

    Nuclear Materials and Energy 22 2020/01

    DOI: 10.1016/j.nme.2019.100673  

    eISSN: 2352-1791

  74. Molecular dynamics study on DNA damage by tritium disintegration Peer-reviewed

    Hiroaki Nakamura, Hisanori Miyanishi, Takuo Yasunaga, Susumu Fujiwara, Tomoko Mizuguchi, Ayako Nakata, Tsuyoshi Miyazaki, Takao Otsuka, Takahiro Kenmotsu, Yuji Hatano, Shinji Saito

    Japanese Journal of Applied Physics 59 (SA) 2020/01/01

    DOI: 10.7567/1347-4065/ab460d  

    ISSN: 0021-4922

    eISSN: 1347-4065

  75. Stable structure of hydrogen atoms trapped in tungsten divacancy Peer-reviewed

    Kazuhito Ohsawa, Takeshi Toyama, Yuji Hatano, Masatake Yamaguchi, Hideo Watanabe

    Journal of Nuclear Materials 527 2019/12/15

    DOI: 10.1016/j.jnucmat.2019.151825  

    ISSN: 0022-3115

  76. Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution Peer-reviewed

    Moeko Nakata, Keisuke Azuma, Akihiro Togari, Qilai Zhou, Mingzhong Zhao, Takeshi Toyama, Yuji Hatano, Naoaki Yoshida, Hideo Watanabe, Masashi Shimada, Dean Buchenauer, Yasuhisa Oya

    Fusion Engineering and Design 146 2096-2099 2019/09

    DOI: 10.1016/j.fusengdes.2019.03.114  

    ISSN: 0920-3796

  77. Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron Peer-reviewed

    Makoto Kobayashi, Masashi Shimada, Chase N. Taylor, Dean Buchenauer, Robert Kolasinski, Takaaki Koyanagi, Yuji Nobuta, Yuji Hatano, Yasuhisa Oya

    Fusion Engineering and Design 146 1624-1627 2019/09

    DOI: 10.1016/j.fusengdes.2019.03.003  

    ISSN: 0920-3796

  78. Kinetics of double strand breaks of DNA in tritiated water evaluated using single molecule observation method Peer-reviewed

    Yuji Hatano, Yuna Konaka, Hiroto Shimoyachi, Takahiro Kenmotsu, Yasuhisa Oya, Hiroaki Nakamura

    Fusion Engineering and Design 146 100-102 2019/09

    DOI: 10.1016/j.fusengdes.2018.11.045  

    ISSN: 0920-3796

  79. Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall

    Joffrin, E., Abduallev, S., Abhangi, M., Abreu, P., Afanasev, V., Afzal, M., Aggarwal, K.M., Ahlgren, T., Aho-Mantila, L., Aiba, N., Airila, M., Alarcon, T., Albanese, R., Alegre, D., Aleiferis, S., Alessi, E., Aleynikov, P., Alkseev, A., Allinson, M., Alper, B., Alves, E., Ambrosino, G., Ambrosino, R., Amosov, V., Andersson Su, e}n, E., Andrews, R., Angelone, M., Anghel, M., Angioni, C., Appel, L., Appelbee, C., Arena, P., Ariola, M., Arshad, S., Artaud, J., Arter, W., Ash, A., Ashikawa, N., Aslanyan, V., Asunta, O., Asztalos, O., Auriemma, F., Austin, Y., Avotina, L., Axton, M., Ayres, C., Baciero, A., Baiao, D., Balboa, I., Balden, M., Balshaw, N., Bandaru, V.K., Banks, J., Baranov, Y.F., Barcellona, C., Barnard, T., Barnes, M., Barnsley, R., Baron Wiechec, A., Barrera Orte, L., Baruzzo, M., Basiuk, V., Bassan, M., Bastow, R., Batista, A., Batistoni, P., Baumane, L., Bauvir, B., Baylor, L., Beaumont, P.S., Beckers, M., Beckett, B., Bekris, N., Beldishevski, M., Bell, K., Belli, F., Belonohy, E., Benayas, J., Bergsaker, H., Bernardo, J., Bernert, M., Berry, M., Bertalot, L., Besiliu, C., Betar, H., Beurskens, M., Bielecki, J., Biewer, T., Bilato, R., Biletskyi, O., Bilkov{\'a}, P., Binda, F., Birkenmeier, G., Bizarro, J.P.S., Bj{\"o}rkas, C., Blackburn, J., Blackman, T.R., Blanchard, P., Blatchford, P., Bobkov, V., Boboc, A., Bogar, O., Bohm, P., Bohm, T., Bolshakova, I., Bolzonella, T., Bonanomi, N., Boncagni, L., Bonfiglio, D., Bonnin, X., Boom, J., Borba, D., Borodin, D., Borodkina, I., Boulbe, C., Bourdelle, C., Bowden, M., Bowman, C., Boyce, T., Boyer, H., Bradnam, S.C., Braic, V., Bravanec, R., Breizman, B., Brennan, D., Breton, S., Brett, A., Brezinsek, S., Bright, M., Brix, M., Broeckx, W., Brombin, M., Bros?awski, A., Brown, B., Brunetti, D., Bruno, E., Buch, J., Buchanan, J., Buckingham, R., Buckley, M., Bucolo, M., Budny, R., Bufferand, H., Buller, S., Bunting, P., Buratti, P., Burckhart, A., Burroughes, G., Buscarino, A., Busse, A., Butcher, D., Butler, B., Bykov, I., Cahyna, P., Calabro, G., Calacci, L., Callaghan, D., Callaghan, J., Calvo, I., Camenen, Y., Camp, P., Campling, D.C., Cannas, B., Capat, A., Carcangiu, S., Card, P., Cardinali, A., Carman, P., Carnevale, D., Carr, M., Carralero, D., Carraro, L., Carvalho, B.B., Carvalho, I., Carvalho, P., Carvalho, D.D., Casson, F.J., Castaldo, C., Catarino, N., Causa, F., Cavazzana, R., Cave-Ayland, K., Cavedon, M., Cecconello, M., Ceccuzzi, S., Cecil, E., Challis, C.D., Chandra, D., Chang, C.S., Chankin, A., Chapman, I.T., Chapman, B., Chapman, S.C., Chernyshova, M., Chiariello, A., Chitarin, G., Chmielewski, P., Chone, L., Ciraolo, G., Ciric, D., Citrin, J., Clairet, F., Clark, M., Clark, E., Clarkson, R., Clay, R., Clements, C., Coad, J.P., Coates, P., Cobalt, A., Coccorese, V., Cocilovo, V., Coelho, R., Coenen, J.W., Coffey, I., Colas, L., Colling, B., Collins, S., Conka, D., Conroy, S., Conway, N., Coombs, D., Cooper, S.R., Corradino, C., Corre, Y., Corrigan, G., Coster, D., Craciunescu, T., Cramp, S., Crapper, C., Crisanti, F., Croci, G., Croft, D., Cromb{\'e}, K., Cruz, N., Cseh, G., Cufar, A., Cullen, A., Curson, P., Curuia, M., Czarnecka, A., Czarski, T., Cziegler, I., Dabirikhah, H., Dal Molin, A., Dalgliesh, P., Dalley, S., Dankowski, J., Darrow, D., David, P., Davies, A., Davis, W., Dawson, K., Day, I., Day, C., De Bock, M., De Castro, A., De Dominici, G., d, De La Cal, E., De La Luna, E., De Masi, G., De Temmerman, G., De Tommasi, G., De Vries, P., Deane, J., Dejarnac, R., Del Sarto, D., Delabie, E., Demerdzhiev, V., Dempsey, A., Den Harder, N., Dendy, R.O., Denis, J., Denner, P., Devaux, S., Devynck, P., Di Maio, F., Di Siena, A., Di Troia, C., Dickinson, D., Dinca, P., Dittmar, T., Dobrashian, J., Doerk, H., Doerner, R.P., Domptail, F., Don, e}, T., Dorling, S.E., Douai, D., Dowson, S., Drenik, A., Dreval, M., Drewelow, P., Drews, P., Duckworth, P., Dumont, R., Dumortier, P., Dunai, D., Dunne, M., ?uran, I., Durodi{\'e}, F., Dutta, P., Duval, B.P., Dux, R., Dylst, K., Edappala, P.V., Edwards, A.M., Edwards, J.S., Eich, T., Eidietis, N., Eksaeva, A., Ellis, R., Ellwood, G., Elsmore, C., Emery, S., Enachescu, M., Ericsson, G., Eriksson, J., Eriksson, F., Eriksson, L.G., Ertmer, S., Esquembri, S., Esquisabel, A.L., Esser, H.G., Ewart, G., Fable, E., Fagan, D., Faitsch, M., Falie, D., Fanni, A., Farahani, A., Fasoli, A., Faugeras, B., Fazinic, S., Felici, F., Felton, R.C., Feng, S., Fernades, A., Fernandes, H., Ferreira, J., Ferreira, D.R., Ferro, G., Fessey, J.A., Ficker, O., Field, A., Fietz, S., Figini, L., Figueiredo, J., Figueiredo, A., Figueiredo, J., Fil, N., Finburg, P., Fischer, U., Fittill, L., Fitzgerald, M., Flammini, D., Flanagan, J., Flinders, K., Foley, S., Fonnesu, N., Fontdecaba, J.M., Formisano, A., Forsythe, L., Fortuna, L., Fransson, E., Frasca, M., Frassinetti, L., Freisinger, M., Fresa, R., Fridstr{\"o}m, R., Frigione, D., Fuchs, V., Fusco, V., Futatani, S., G{\'a}l, K., Galassi, D., Ga?azka, K., Galeani, S., Gallart, D., Galvao, R., Gao, Y., Garcia, J., Garcia-Carrasco, A., Garcia-Munoz, M., Gardener, M., Garzotti, L., Gaspar, J., Gaudio, P., Gear, D., Gebhart, T., Gee, S., Geiger, B., Gelfusa, M., George, R., Gerasimov, S., Gervasini, G., Gethins, M., Ghani, Z., Ghate, M., Gherendi, M., Ghezzi, F., Giacalone, J.C., Giacomelli, L., Giacometti, G., Gibson, K., Giegerich, T., Gil, L., Gilbert, M.R., Gin, D., Giovannozzi, E., Giroud, C., Gl{\"o}ggler, S., Goff, J., Gohil, P., Goloborod{'}Ko, V., Goloborodko, V., Gomes, R., Goncalves, B., Goniche, M., Goodyear, A., Gorini, G., G{\"o}rler, T., Goulding, R., Goussarov, A., Graham, B., Graves, J.P., Greuner, H., Grierson, B., Griffiths, J., Griph, S., Grist, D., Groth, M., Grove, R., Gruca, M., Guard, D., Gu{\'e}rard, C., Guillemaut, C., Guirlet, R., Gulati, S., Gurl, C., Gutierrez-Milla, A., Utoh, H.H., Hackett, L., Hacquin, S., Hager, R., Hakola, A., Halitovs, M., Hall, S., Hallworth-Cook, S., Ham, C., Hamed, M., Hamilton, N., Hamlyn-Harris, C., Hammond, K., Hancu, G., Harrison, J., Harting, D., Hasenbeck, F., Hatano, Y., Hatch, D.R., Haupt, T., Hawes, J., Hawkes, N.C., Hawkins, J., Hawkins, P., Hazel, S., Heesterman, P., Heinola, K., Hellesen, C., Hellsten, T., Helou, W., Hemming, O., Hender, T.C., Henderson, S.S., Henderson, S.S., Henderson, M., Henriques, R., Hepple, D., Herfindal, J., Hermon, G., Hidalgo, C., Higginson, W., Highcock, E.G., Hillesheim, J., Hillis, D., Hizanidis, K., Hjalmarsson, A., Ho, A., Hobirk, J., Hogben, C.H.A., Hogeweij, G.M.D., Hollingsworth, A., Hollis, S., H{\"o}lzl, M., Honore, J.-J., Hook, M., Hopley, D., Hor{\'a}?ek, J., Hornung, G., Horton, A., Horton, L.D., Horvath, L., Hotchin, S.P., Howell, R., Hubbard, A., Huber, A., Huber, V., Huddleston, T.M., Hughes, M., Hughes, J., Huijsmans, G.T.A., Huynh, P., Hynes, A., Igaune, I., Iglesias, D., Imazawa, N., Imri?ek, M., Incelli, M., Innocente, P., Ivanova-Stanik, I., Ivings, E., Jachmich, S., Jackson, A., Jackson, T., Jacquet, P., Jansons, J., Jaulmes, F., Jednor{\'o}g, S., Jenkins, I., Jepu, I., Johnson, T., Johnson, R., Johnston, J., Joita, L., Joly, J., Jonasson, E., Jones, T., Jones, C., Jones, L., Jones, G., Jones, N., Juvonen, M., Hoshino, K.K., Kallenbach, A., Kalsey, M., Kaltiaisenaho, T., Kamiya, K., Kaniewski, J., Kantor, A., Kappatou, A., Karhunen, J., Karkinsky, D., Kaufman, M., Kaveney, G., Kazakov, Y., Kazantzidis, V., Keeling, D.L., Keenan, F.P., Kempenaars, M., Kent, O., Kent, J., Keogh, K., Khilkevich, E., Kim, H.-T., Kim, H.T., King, R., King, D., Kinna, D.J., Kiptily, V., Kirk, A., Kirov, K., Kirschner, A., Kizane, G., Klas, M., Klepper, C., Klix, A., Knight, M., Knight, P., Knipe, S., Knott, S., Kobuchi, T., K{\"o}chl, F., Kocsis, G., Kodeli, I., Koechl, F., Kogut, D., Koivuranta, S., Kolesnichenko, Y., Kollo, Z., Kominis, Y., K{\"o}ppen, M., Korolczuk, S., Kos, B., Koslowski, H.R., Kotschenreuther, M., Koubiti, M., Kovaldins, R., Kovanda, O., Kowalska-Strz?ciwilk, E., Krasilnikov, A., Krasilnikov, V., Krawczyk, N., Kresina, M., Krieger, K., Krivska, A., Kruezi, U., Ksia?ek, I., Kukushkin, A., Kundu, A., Kurki-Suonio, T., Kwak, S., Kwon, O.J., Laguardia, L., Lahtinen, A., Laing, A., Lalousis, P., Lam, N., Lamb, C., Lambertz, H.T., Lang, P.T., Lanthaler, S., Lascas Neto, E., ?aszy?ska, E., Lawless, R., Lawson, K.D., Lazaros, A., Lazzaro, E., Leach, R., Learoyd, G., Leerink, S., Lefebvre, X., Leggate, H.J., Lehmann, J., Lehnen, M., Leichauer, P., Leichtle, D., Leipold, F., Lengar, I., Lennholm, M., Lepiavko, B., Leppanen, J., Lerche, E., Lescinskis, A., Lescinskis, B., Lesnoj, S., Leyland, M., Leysen, W., Li, Y., Li, L., Liang, Y., Likonen, J., Linke, J., Linsmeier, C., Lipschultz, B., Litaudon, X., Liu, G., Lloyd, B., Lo Schiavo, V.P., Loarer, T., Loarte, A., Lomanowski, B., Lomas, P.J., L{\"o}nnroth, J., L{\'o}pez, J.M., Lorenzini, R., Losada, U., Loughlin, M., Lowry, C., Luce, T., Lucock, R., Lukin, A., Luna, C., Lungaroni, M., Lungu, C.P., Lungu, M., Lunniss, A., Lunt, T., Lupelli, I., Lutsenko, V., Lyssoivan, A., Macheta, P., Macusova, E., Magesh, B., Maggi, C., Maggiora, R., Mahesan, S., Maier, H., Mailloux, J., Maingi, R., Makwana, R., Malaquias, A., Malinowski, K., Malizia, A., Manas, P., Manduchi, G., Manso, M.E., Mantica, P., Mantsinen, M., Manzanares, A., Maquet, P., Marandet, Y., Marcenko, N., Marchetto, C., Marchuk, O., Marconato, N., Mariani, A., Marin, M., Marinelli, M., Marinucci, M., Markovi?, T., Marocco, D., Marot, L., Marsh, J., Martin, A., Martin De Aguilera, A., Martin-Solis, J.R., Martone, R., Martynova, Y., Maruyama, S., Maslov, M., Matejcik, S., Mattei, M., Matthews, G.F., Matveev, D., Matveeva, E., Mauriya, A., Maviglia, F., May-Smith, T., Mayer, M., Mayoral, M.L., Mazon, D., Mazzotta, C., McAdams, R., McCarthy, P.J., McClements, K.G., McCormack, O., McCullen, P.A., McDonald, D., McHardy, M., McKean, R., McKehon, J., McNamee, L., Meadowcroft, C., Meakins, A., Medley, S., Meigh, S., Meigs, A.G., Meisl, G., Meiter, S., Meitner, S., Meneses, L., Menmuir, S., Mergia, K., Merle, A., Merriman, P., Mertens, P., Meshchaninov, S., Messiaen, A., Meyer, H., Michling, R., Milanesio, D., Militello, F., Militello-Asp, E., Milocco, A., Miloshevsky, G., Mink, F., Minucci, S., Miron, I., Mistry, S., Miyoshi, Y., Mlyn{\'a}?, J., Moiseenko, V., Monaghan, P., Monakhov, I., Moon, S., Mooney, R., Moradi, S., Morales, J., Moran, J., Mordijck, S., Moreira, L., Moro, F., Morris, J., Moser, L., Mosher, S., Moulton, D., Mrowetz, T., Muir, A., Muraglia, M., Murari, A., Muraro, A., Murphy, S., Muscat, P., Muthusonai, N., Myers, C., Asakura, N.N., N{'}Konga, B., Nabais, F., Naish, R., Naish, J., Nakano, T., Napoli, F., Nardon, E., Naulin, V., Nave, M.F.F., Nedzelskiy, I., Nemtsev, G., Nesenevich, V., Nespoli, F., Neto, A., Neu, R., Neverov, V.S., Newman, M., Ng, S., Nicassio, M., Nielsen, A.H., Nina, D., Nishijima, D., Noble, C., Nobs, C.R., Nocente, M., Nodwell, D., Nordlund, K., Nordman, H., Normanton, R., Noterdaeme, J.M., Nowak, S., Nunes, I., O{'}Gorman, T., O{'}Mullane, M., Oberkofler, M., Oberparleiter, M., Odupitan, T., Ogawa, M.T., Okabayashi, M., Oliver, H., Olney, R., Omoregie, L., Ongena, J., Orsitto, F., Orszagh, J., Osborne, T., Otin, R., Owen, A., Owen, T., Paccagnella, R., Packer, L.W., Pajuste, E., Pamela, S., Panja, S., Papp, P., Papp, G., Parail, V., Pardanaud, C., Parra Diaz, F., Parsloe, A., Parsons, N., Parsons, M., Pasqualotto, R., Passeri, M., Patel, A., Pathak, S., Patten, H., Pau, A., Pautasso, G., Pavlichenko, R., Pavone, A., Pawelec, E., Paz Soldan, C., Peackoc, A., Pehkonen, S.-P., Peluso, E., Penot, C., Penzo, J., Pepperell, K., Pereira, R., Perelli Cippo, E., Perez Von Thun, C., Pericoli, V., Peruzzo, S., Peterka, M., Petersson, P., Petravich, G., Petre, A., Petr?ilka, V., Philipps, V., Pigatto, L., Pillon, M., Pinches, S., Pintsuk, G., Piovesan, P., Pires De Sa, W., Pires Dos Reis, A., Piron, L., Piron, C., Pironti, A., Pisano, F., Pitts, R., Plyusnin, V., Poli, F.M., Pomaro, N., Pompilian, O.G., Pool, P., Popovichev, S., Poradzi?ski, M., Porfiri, M.T., Porosnicu, C., Porton, M., Possnert, G., Potzel, S., Poulipoulis, G., Powell, T., Prajapati, V., Prakash, R., Predebon, I., Prestopino, G., Price, D., Price, M., Price, R., Primetzhofer, D., Prior, P., Pucella, G., Puglia, P., Puiatti, M.E., Purahoo, K., Pusztai, I., P, u}tterich, T., Rachlew, E., Rack, M., Ragona, R., Rainford, M., Raj, P., Rakha, A., Ramogida, G., Ranjan, S., Rapson, C.J., Rasmussen, D., Rasmussen, J.J., Rathod, K., Ratt{\'a}, G., Ratynskaia, S., Ravera, G., Rebai, M., Reed, A., R{\'e}fy, D., Regana, J., Reich, M., Reid, N., Reimold, F., Reinhart, M., Reinke, M., Reiser, D., Rendell, D., Reux, C., Reyes Cortes, S.D.A., Reynolds, S., Ricci, D., Richiusa, M., Rigamonti, D., Rimini, F.G., Risner, J., Riva, M., Rivero-Rodriguez, J., Roach, C., Robins, R., Robinson, S., Robson, D., Rodionov, R., Rodrigues, P., Rodriguez, J., Rohde, V., Romanelli, M., Romanelli, F., Romanelli, S., Romazanov, J., Rowe, S., Rubel, M., Rubinacci, G., Rubino, G., Ruchko, L., Ruset, C., Rzadkiewicz, J., Saarelma, S., Sabot, R., S{\'a}ez, X., Safi, E., Sahlberg, A., Saibene, G., Saleem, M., Salewski, M., Salmi, A., Salmon, R., Salzedas, F., Samm, U., Sandiford, D., Santa, P., Santala, M.I.K., Santos, B., Santucci, A., Sartori, F., Sartori, R., Sauter, O., Scannell, R., Schluck, F., Schlummer, T., Schmid, K., Schmuck, S., Sch{\"o}pf, K., Schweinzer, J., Schw{\"o}rer, D., Scott, S.D., Sergienko, G., Sertoli, M., Shabbir, A., Sharapov, S.E., Shaw, A., Sheikh, H., Shepherd, A., Shevelev, A., Shiraki, D., Shumack, A., Sias, G., Sibbald, M., Sieglin, B., Silburn, S., Silva, J., Silva, A., Silva, C., Silvagni, D., Simmons, P., Simpson, J., Sinha, A., Sipila, S.K., Sips, A.C.C., Sir{\'e}n, P., Sirinelli, A., Sj{\"o}strand, H., Skiba, M., Skilton, R., Skvara, V., Slade, B., Smith, R., Smith, P., Smith, S.F., Snoj, L., Soare, S., Solano, E.R., Somers, A., Sommariva, C., Sonato, P., Sos, M., Sousa, J., Sozzi, C., Spagnolo, S., Sparapani, P., Spelzini, T., Spineanu, F., Sprada, D., Sridhar, S., Stables, G., Stallard, J., Stamatelatos, I., Stamp, M.F., Stan-Sion, C., Stancar, Z., Staniec, P., Stank?nas, G., Stano, M., Stavrou, C., Stefanikova, E., Stepanov, I., Stephen, A.V., Stephen, M., Stephens, J., Stevens, B., Stober, J., Stokes, C., Strachan, J., Strand, P., Strauss, H.R., Str{\"o}m, P., Studholme, W., Subba, F., Suchkov, E., Summers, H.P., Sun, H., Sutton, N., Svensson, J., Sytnykov, D., Szabolics, T., Szepesi, G., Suzuki, T.T., Tabar{\'e}s, F., Tadic, T., Tal, B., T{\'a}l, B., Tala, T., Taliercio, C., Tallargio, A., Tanaka, K., Tang, W., Tardocchi, M., Tatali, R., Taylor, D., Tegnered, D., Telesca, G., Teplova, N., Teplukhina, A., Terranova, D., Terry, C., Testa, D., Tholerus, E., Thomas, J., Thompson, V.K., Thornton, A., Tierens, W., Tiseanu, I., Tojo, H., Tokitani, M., Tolias, P., Tome?, M., Trimble, P., Tripsky, M., Tsalas, M., Tsavalas, P., Tskhakaya, D., Tskhakaya Jun, D., Turner, I., Turner, M.M., Turnyanskiy, M., Tvalashvili, G., Tyshchenko, M., Uccello, A., Uljanovs, J., Urano, H., Urban, A., Urbanczyk, G., Uytdenhouwen, I., Vadgama, A., Valcarcel, D., Vale, R., Valentinuzzi, M., Valerii, K., Valisa, M., allejos Olivares, P., Valovic, M., Van Eester, D., Van Renterghem, W., Van Rooij, G.J., Varje, J., Vartanian, S., Vasava, K., Vasilopoulou, T., Vecsei, M., Vega, J., Ventre, S., Verdoolaege, G., Verona, C., Verona Rinati, G., Veshchev, E., Vianello, N., Vicente, J., Viezzer, E., Villari, S., Villone, F., Vincent, M., Vincenzi, P., Vinyar, I., Viola, B., Vitins, A., Vizvary, Z., Vlad, M., Voitsekhovitch, I., Voltolina, D., Von Toussain, U, d, Vo, a}?ek, P., Vuksic, M., Wakeling, B., Waldon, C., Walkden, N., Walker, R., Walker, M., Walsh, M., Wang, N., Wang, E., Wang, N., Warder, S., Warren, R., Waterhouse, J., Watts, C., Wauters, T., Webb, M., Weckmann, A., Weiland, J., Weiland, M., Weisen, H., Weiszflog, M., Welch, P., West, A., Wheatley, M., Wheeler, S., Whitehead, A.M., Whittaker, D., Widdowson, A.M., Wiesen, S., Wilkie, G., Williams, J., Willoughby, D., Wilson, J., Wilson, I., Wilson, H.R., Wischmeier, M., Withycombe, A., Witts, D., Wolfrum, E., Wood, R., Woodley, R., Woodley, C., Wray, S., Wright, J.C., Wright, P., Wukitch, S., Wynn, A., Xiang, L., Xu, T., Xue, Y., Yadikin, D., Yakovenko, Y., Yanling, W., Yavorskij, V., Young, I., Young, R., Young, D., Zacks, J., Zagorski, R., Zaitsev, F.S., Zakharov, L., Zanino, R., Zarins, A., Zarins, R., Zarzoso Fernandez, D., Zastrow, K.D., Zerbini, M., Zhang, W., Zhou, Y., Zilli, E., Zocco, A., Zoita, V., Zoletnik, S., Zwingmann, W., Zychor, I.

    Nuclear Fusion 59 (11) 2019

    DOI: 10.1088/1741-4326/ab2276  

    ISSN: 1741-4326 0029-5515

  80. Computational strategy for studying structural change of tritium-substituted macromolecules by a beta decay to helium-3

    Fujiwara Susumu, Nakamura Hiroaki, Li Haolun, Miyanishi Hisanori, Mizuguchi Tomoko, Yasunaga Takuo, Otsuka Takao, Hatano Yuji, Saito Shinji

    Journal of Advanced Simulation in Science and Engineering 6 (1) 94-99 2019

    Publisher: Japan Society for Simulation Technology

    DOI: 10.15748/jasse.6.94  

    More details Close

    <p>We propose a computational strategy for investigating structural change of tritium-substituted macromolecules. Effects of radiation on macromolecules such as polymeric materials and DNA are classified into three categories: (1) direct action, (2) indirect action, and (3) decay effect. In this study, we focus on the decay effect exclusively. After a beta decay of substituted tritium in macromolecules to helium-3, the generated inert helium-3 is assumed to be deleted quickly. To get an insight into the decay effect to the damage of macromolecules, we perform molecular dynamics simulations of tritium-deleted macromolecules and analyze their structural change. Preliminary simulation results of decay effect on polymeric materials and DNA are presented.</p>

  81. Computational strategy for studying structural change of tritium-substituted macromolecules by a beta decay to helium-3

    Susumu Fujiwara, Hiroaki Nakamura, Haolun Li, Hisanori Miyanishi, Tomoko Mizuguchi, Takuo Yasunaga, Takao Otsuka, Yuji Hatano, Shinji Saito

    JOURNAL OF ADVANCED SIMULATION IN SCIENCE AND ENGINEERING 6 (1) 94-99 2019

    DOI: 10.15748/jasse.6.94  

    ISSN: 2188-5303

  82. Structural Changes in Tritium-Substituted Polymeric Materials by Beta Decays: A Molecular Dynamics Study

    Haolun Li, Susumu Fujiwara, Hiroaki Nakamura, Tomoko Mizuguchi, Takuo Yasunaga, Takao Otsuka, Takahiro Kenmotsu, Yuji Hatano, Shinji Saito

    PLASMA AND FUSION RESEARCH 14 2019

    DOI: 10.1585/pfr.14.3401106  

    ISSN: 1880-6821

  83. Effect of Damage Introduction and He Existence on D Retention in Tungsten by High Flux D Plasma Exposure Peer-reviewed

    Yasuhisa Oya, Keisuke Azuma, Akihiro Togari, Moeko Nakata, Qilai Zhou, Mingzhong Zhao, Tatsuya Kuwabara, Noriyasu Ohno, Miyuki Yajima, Yuji Hatano, Takeshi Toyama

    Lecture Notes in Networks and Systems 53 89-96 2019

    DOI: 10.1007/978-3-319-99834-3_12  

    ISSN: 2367-3370

    eISSN: 2367-3389

  84. Deuterium Removal Efficiency in Tungsten as a Function of Hydrogen Ion Beam Fluence and Temperature Peer-reviewed

    Mingzhong Zhao, Qilai Zhou, Moeko Nakata, Akihiro Togari, Fei Sun, Yuji Hatano, Naoaki Yoshida, Yasuhisa Oya

    Lecture Notes in Networks and Systems 53 20-27 2019

    DOI: 10.1007/978-3-319-99834-3_3  

    ISSN: 2367-3370

    eISSN: 2367-3389

  85. Effect of C-He simultaneous implantation on deuterium retention in damaged W by Fe implantation Peer-reviewed

    Keisuke Azuma, Akihiro Togari, Qilai Zhou, Yuji Hatano, Naoaki Yoshida, Masashi Shimada, Chase N. Taylor, Dean Buchenauer, Robert Kolasinski, Takumi Chikada, Yasuhisa Oya

    Fusion Engineering and Design 137 10-14 2018/12

    DOI: 10.1016/j.fusengdes.2018.08.002  

    ISSN: 0920-3796

  86. Plasma-Wall Interaction on the Divertor Tiles of JET ITER-Like Wall from the Viewpoint of Micro/Nanoscopic Observations Peer-reviewed

    M. Tokitani, M. Miyamoto, S. Masuzaki, R. Sakamoto, Y. Oya, Y. Hatano, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, K. Isobe, N. Asakura, A. Widdowson, K. Heinola, M. Rubel

    Fusion Engineering and Design 136 199-204 2018/11

    DOI: 10.1016/j.fusengdes.2018.01.051  

    ISSN: 0920-3796

  87. Dust generation in tokamaks: Overview of beryllium and tungsten dust characterisation in JET with the ITER-like wall Peer-reviewed

    M. Rubel, A. Widdowson, J. Grzonka, E. Fortuna-Zalesna, Sunwoo Moon, P. Petersson, N. Ashikawa, N. Asakura, D. Hamaguchi, Y. Hatano, K. Isobe, S. Masuzaki, H. Kurotaki, Y. Oya, M. Oyaidzu, M. Tokitani

    Fusion Engineering and Design 136 579-586 2018/11

    DOI: 10.1016/j.fusengdes.2018.03.027  

    ISSN: 0920-3796

  88. Effects of baking in deuterium atmosphere on tritium removal from tungsten Peer-reviewed

    Yuji Nobuta, Yuji Hatano, Yuji Torikai, Masato Nakayama

    Fusion Engineering and Design 136 674-677 2018/11

    DOI: 10.1016/j.fusengdes.2018.03.054  

    ISSN: 0920-3796

  89. Deuterium absorption in reduced activation ferritic/martensitic steel F82H under exposure to D<inf>2</inf>O vapor/water at room temperature Peer-reviewed

    V. Kh Alimov, Y. Hatano, K. Sugiyama, M. Zibrov, T. Schwarz-Selinger, W. Jacob

    Journal of Nuclear Materials 507 54-58 2018/08/15

    DOI: 10.1016/j.jnucmat.2018.04.035  

    ISSN: 0022-3115

  90. Surface or bulk He existence effect on deuterium retention in Fe ion damaged W Peer-reviewed

    Yasuhisa Oya, Shodai Sakurada, Keisuke Azuma, Qilai Zhou, Akihiro Togari, Sosuke Kondo, Tatsuya Hinoki, Naoaki Yoshida, Dean Buchenauer, Robert Kolasinski, Masashi Shimada, Chase N. Taylor, Takumi Chikada, Yuji Hatano

    Nuclear Materials and Energy 16 217-220 2018/08

    DOI: 10.1016/j.nme.2018.06.018  

    eISSN: 2352-1791

  91. Deuterium retention behavior in simultaneously He+–D<inf>2</inf>+ implanted tungsten Peer-reviewed

    Qilai Zhou, Keisuke Azuma, Akihiro Togari, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Masanori Hara, Yuji Hatano, Yasuhisa Oya

    Nuclear Materials and Energy 16 76-81 2018/08

    DOI: 10.1016/j.nme.2018.06.012  

    eISSN: 2352-1791

  92. Monte Carlo simulation of tritium beta-ray induced X-ray spectrum in various gases Peer-reviewed

    Masanori Hara, Ryota Uchikawa, Yuji Hatano, Masao Matsuyama, Tsukasa Aso, Tomohiko Kawakami, Takeshi Ito

    Fusion Engineering and Design 131 125-129 2018/06

    DOI: 10.1016/j.fusengdes.2018.04.080  

    ISSN: 0920-3796

  93. Surface modification and deuterium retention in reduced-activation steels exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas Peer-reviewed

    V. Kh Alimov, O. V. Ogorodnikova, Y. Hatano, Yu M. Gasparyan, V. S. Efimov, M. Mayer, Z. Zhou, M. Oyaizu, K. Isobe, H. Nakamura, T. Hayashi

    Journal of Nuclear Materials 502 1-8 2018/04

    DOI: 10.1016/j.jnucmat.2018.01.060  

    ISSN: 0022-3115

  94. Helium retention behavior in simultaneously He+-H<inf>2</inf>+ irradiated tungsten Peer-reviewed

    Qilai Zhou, Keisuke Azuma, Akihiro Togari, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Masanori Hara, Yuji Hatano, Yasuhisa Oya

    Journal of Nuclear Materials 502 289-294 2018/04

    DOI: 10.1016/j.jnucmat.2018.02.035  

    ISSN: 0022-3115

  95. 14 MeV calibration of JET neutron detectors-phase 1: Calibration and characterization of the neutron source

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    Nuclear Fusion 58 (2) 2018

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  99. Impact of annealing on deuterium retention behavior in damaged W Peer-reviewed

    Shodai Sakurada, Yuki Uemura, Hiroe Fujita, Keisuke Azuma, Takeshi Toyama, Naoaki Yoshida, Tatsuya Hinoki, Sosuke Kondo, Yuji Hatano, Masashi Shimada, Dean Buchenauer, Takumi Chikada, Yasuhisa Oya

    Fusion Science and Technology 72 (4) 785-788 2017/11

    DOI: 10.1080/15361055.2017.1350480  

    ISSN: 1536-1055

  100. Effect of sequential Fe2+ − C+ implantation on deuterium retention in W Peer-reviewed

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    Fusion Engineering and Design 124 231-234 2017/11

    DOI: 10.1016/j.fusengdes.2017.05.078  

    ISSN: 0920-3796

  101. Hydrogen isotope retention and permeation in neutron-irradiated tungsten and tungsten alloys under PHENIX collaboration Peer-reviewed

    Masashi Shimada, Yasuhisa Oya, Dean A. Buchenauer, Yuji Hatano

    Fusion Science and Technology 72 (4) 652-659 2017/11

    DOI: 10.1080/15361055.2017.1347468  

    ISSN: 1536-1055

  102. Recent R&amp;D results on fusion nuclear technology for ITER and DEMO reactor in Japan Peer-reviewed

    Toshihiko Yamanishi, Norikiyo Koizumi, Masataka Nakahira, Yoshihiko Nunoya, Satoshi Suzuki, Hiroyuki Tobari, Mieko Kashiwagi, Takaaki Isono, Takashi Inoue, Makoto Sugimoto, Yoshinori Kusama, Yoshinori Kawamura, Hiroyasu Tanigawa, Masaru Nakamichi, Takashi Nozawa, Tsuyoshi Hoshino, Yoshio Ueda, Yuji Hatano, Takeo Muroga, Satoshi Fukada

    Fusion Science and Technology 72 (3) 233-241 2017/10

    DOI: 10.1080/15361055.2017.1330625  

    ISSN: 1536-1055

  103. Effect of helium irradiation on deuterium permeation behavior in tungsten International-journal International-coauthorship Peer-reviewed

    Yuki Uemura, Shodai Sakurada, Hiroe Fujita, Keisuke Azuma, Quilai Zhou, Takumi Chikada, Yasuhisa Oya, Yuji Hatano, Naoaki Yoshida, Hideo Watanabe, Makoto Oyaizu, Kanetsugu Isobe, Masashi Shimada, Dean Buchenauer, Robert Kolasinski

    Journal of Nuclear Materials 490 242-246 2017/07/01

    DOI: 10.1016/j.jnucmat.2017.04.041  

    ISSN: 0022-3115

    eISSN: 1873-4820

  104. Investigation of irradiation effects on highly integrated leading-edge electronic components of diagnostics and control systems for LHD deuterium operation Peer-reviewed

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    Nuclear Fusion 57 (8) 2017/06/14

    DOI: 10.1088/1741-4326/aa71e8  

    ISSN: 0029-5515

    eISSN: 1741-4326

  105. Deuterium retention in helium and neutron irradiated molybdenum Peer-reviewed

    C. N. Taylor, Y. Yamauchi, M. Shimada, Y. Oya, Y. Hatano

    Fusion Science and Technology 71 (4) 491-495 2017/05

    DOI: 10.1080/15361055.2016.1273699  

    ISSN: 1536-1055

  106. Development of H, D, T simultaneous TDS measurement system and H, D, T retention behavior for DT gas exposed Tungsten installed in LHD plasma campaign Peer-reviewed

    Yasuhisa Oya, Cui Hu, Hiroe Fujita, Kenta Yuyama, Shodai Sakurada, Yuki Uemura, Suguru Masuzaki, Masayuki Tokitani, Miyuki Yajima, Yuji Hatano, Takumi Chikada

    Fusion Science and Technology 71 (3) 351-356 2017/04

    DOI: 10.1080/15361055.2017.1291039  

    ISSN: 1536-1055

  107. Estimation of tritium permeation rate to cooling water in fusion DEMO condition Peer-reviewed

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    Fusion Science and Technology 71 (3) 261-267 2017/04

    DOI: 10.1080/15361055.2017.1288423  

    ISSN: 1536-1055

  108. Micro-/nano-characterization of the surface structures on the divertor tiles from JET ITER-like wall Peer-reviewed

    M. Tokitani, M. Miyamoto, S. Masuzaki, Y. Fujii, R. Sakamoto, Y. Oya, Y. Hatano, T. Otsuka, M. Oyaidzu, H. Kurotaki, T. Suzuki, D. Hamaguchi, K. Isobe, N. Asakura, A. Widdowson, M. Rubel

    Fusion Engineering and Design 116 1-4 2017/03/01

    DOI: 10.1016/j.fusengdes.2017.01.002  

    ISSN: 0920-3796

  109. Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition Peer-reviewed

    Kazunari Katayama, Youji Someya, Kenji Tobita, Hirofumi Nakamura, Hisashi Tanigawa, Makoto Nakamura, Nobuyuki Asakura, Kazuo Hoshino, Takumi Chikada, Yuji Hatano, Satoshi Fukada

    Fusion Science and Technology 71 (3) 261-267 2017/03

    Publisher: Informa UK Limited

    DOI: 10.1080/15361055.2017.1288423  

    ISSN: 1943-7641

    eISSN: 1943-7641

  110. Efficient generation of energetic ions in multi-ion plasmas by radio-frequency heating

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    Nature Physics 13 (10) 2017

    DOI: 10.1038/nphys4167  

    ISSN: 1745-2481 1745-2473

  111. Overview of the JET results in support to ITER

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Uytdenhouwen, I., Vadgama, A.P., Valcarcel, D., Valentinuzzi, M., Valisa, M., allejos Olivares, P., Valovic, M., Van De Mortel, M., Van Eester, D., Van Renterghem, W., Van Rooij, G.J., Varje, J., Varoutis, S., Vartanian, S., Vasava, K., Vasilopoulou, T., Vega, J., Verdoolaege, G., Verhoeven, R., Verona, C., Verona Rinati, G., Veshchev, E., Vianello, N., Vicente, J., Viezzer, E., Villari, S., Villone, F., Vincenzi, P., Vinyar, I., Viola, B., Vitins, A., Vizvary, Z., Vlad, M., Voitsekhovitch, I., V, a}?ek, P., Vora, N., Vu, T., Pires De Sa, W., W, Wakeling, B., Waldon, C.W.F., Walkden, N., Walker, M., Walker, R., Walsh, M., Wang, E., Wang, N., Warder, S., Warren, R.J., Waterhouse, J., Watkins, N.W., Watts, C., Wauters, T., Weckmann, A., Weiland, J., Weisen, H., Weiszflog, M., Wellstood, C., West, A.T., Wheatley, M.R., Whetham, S., Whitehead, A.M., Whitehead, B.D., Widdowson, A.M., Wiesen, S., Wilkinson, J., Williams, J., Williams, M., Wilson, A.R., Wilson, D.J., Wilson, H.R., Wilson, J., Wischmeier, M., Withenshaw, G., Withycombe, A., Witts, D.M., Wood, D., Wood, R., Woodley, C., Wray, S., Wright, J., Wright, J.C., Wu, J., Wukitch, S., Wynn, A., Xu, T., Yadikin, D., Yanling, W., Yao, L., Yavorskij, V., Yoo, M.G., Young, C., Young, D., Young, I.D., Young, R., Zacks, J., Zagorski, R., Zaitsev, F.S., Zanino, R., Zarins, A., Zastrow, K.D., Zerbini, M., Zhang, W., Zhou, Y., Zilli, E., Zoita, V., Zoletnik, S., Zychor, I.

    Nuclear Fusion 57 (10) 2017

    DOI: 10.1088/1741-4326/aa5e28  

    ISSN: 1741-4326 0029-5515

  112. Analyses of microstructure, composition and retention of hydrogen isotopes in divertor tiles of JET with the ITER-like wall Peer-reviewed

    S. Masuzaki, M. Tokitani, T. Otsuka, Y. Oya, Y. Hatano, M. Miyamoto, R. Sakamoto, N. Ashikawa, S. Sakurada, Y. Uemura, K. Azuma, K. Yumizuru, M. Oyaizu, T. Suzuki, H. Kurotaki, D. Hamaguchi, K. Isobe, N. Asakura, A. Widdowson, K. Heinola, S. Jachmich, M. Rubel

    Physica Scripta 2017 (T170) 2017

    DOI: 10.1088/1402-4896/aa8bcc  

    ISSN: 0031-8949

    eISSN: 1402-4896

  113. Development of a compact divertor plasma simulator for plasma-wall interaction studies on neutron-irradiated materials Peer-reviewed

    Noriyasu Ohno, Tatsuya Kuwabara, Makoto Takagi, Ryo Nishimura, Miyuki Yajima, Akio Sagara, Takeshi Toyama, Katuya Suzuki, Hiroaki Kurishita, Tatsuo Shikama, Yuji Hatano, Naoaki Yoshida

    Plasma and Fusion Research 12 2017

    DOI: 10.1585/pfr.12.1405040  

    eISSN: 1880-6821

  114. Effect of impurity deposition layer formation on D retention in LHD plasma exposed W Peer-reviewed

    Y. Oya, H. Fujita, C. Hu, Y. Uemura, S. Sakurada, K. Yuyama, X. Li, Y. Hatano, N. Yoshida, H. Watanabe, Y. Nobuta, Y. Yamauchi, M. Tokitani, S. Masuzaki, T. Chikada

    Nuclear Materials and Energy 9 84-88 2016/12/01

    DOI: 10.1016/j.nme.2016.07.005  

    eISSN: 2352-1791

  115. Recent progress of hydrogen isotope behavior studies for neutron or heavy ion damaged W Peer-reviewed

    Yasuhisa Oya, Yuji Hatano, Masashi Shimada, Dean Buchenauer, Robert Kolasinski, Brad Merrill, Sosuke Kondo, Tatsuya Hinoki, Vladimir Kh Alimov

    Fusion Engineering and Design 113 211-215 2016/12/01

    DOI: 10.1016/j.fusengdes.2016.08.004  

    ISSN: 0920-3796

  116. Influence of displacement damages on deuterium retention in reduced activation ferritic/martensitic steels F82H and Eurofer97 Peer-reviewed

    Vladimir Kh Alimov, Yuji Hatano, Kazuyoshi Sugiyama, Sosuke Kondo, Tatsuya Hinoki, Masayuki Tokitani

    Fusion Engineering and Design 113 336-339 2016/12/01

    DOI: 10.1016/j.fusengdes.2016.02.060  

    ISSN: 0920-3796

  117. Influence of hydrogen addition to a sweep gas on tritium behavior in a blanket module containing Li<inf>2</inf>TiO<inf>3</inf> pebbles Peer-reviewed

    K. Katayama, Y. Someya, K. Tobita, S. Fukada, Y. Hatano, T. Chikada

    Fusion Engineering and Design 113 221-226 2016/12/01

    DOI: 10.1016/j.fusengdes.2016.08.031  

    ISSN: 0920-3796

  118. Review of recent japanese activities on tritium accountability in fusion reactors Peer-reviewed

    Satoshi Fukada, Yasuhisa Oya, Yuji Hatano

    Fusion Engineering and Design 113 231-235 2016/12/01

    DOI: 10.1016/j.fusengdes.2016.08.029  

    ISSN: 0920-3796

  119. Dependence of CuO particle size and diameter of reaction tubing on tritium recovery for tritium safety operation Peer-reviewed

    Cui Hu, Yuki Uemura, Kenta Yuyama, Hiroe Fujita, Shodai Sakurada, Keisuke Azuma, Akira Taguchi, Masanori Hara, Yuji Hatano, Takumi Chikada, Yasuhisa Oya

    Fusion Engineering and Design 113 313-317 2016/12/01

    DOI: 10.1016/j.fusengdes.2016.05.023  

    ISSN: 0920-3796

    eISSN: 1873-7196

  120. Tritium burning in inertial electrostatic confinement fusion facility Peer-reviewed

    Masami Ohnishi, Yasushi Yamamoto, Hodaka Osawa, Yuji Hatano, Yuji Torikai, Isao Murata, Keita Kamakura, Masaaki Onishi, Keiji Miyamoto, Hiroki Konda, Kai Masuda, Eiki Hotta

    Fusion Engineering and Design 109-111 1709-1713 2016/11/01

    DOI: 10.1016/j.fusengdes.2015.10.025  

    ISSN: 0920-3796

  121. Surface modification and sputtering erosion of reduced activation ferritic martensitic steel F82H exposed to low-energy, high flux deuterium plasma Peer-reviewed

    V. Kh Alimov, Y. Hatano, N. Yoshida, H. Watanabe, M. Oyaidzu, M. Tokitani, T. Hayashi

    Nuclear Materials and Energy 7 25-32 2016/05/01

    DOI: 10.1016/j.nme.2016.01.001  

    eISSN: 2352-1791

  122. Impact of temperature during He+ implantation on deuterium retention in tungsten, tungsten with carbon deposit and tungsten carbide Peer-reviewed

    Yasuhisa Oya, Misaki Sato, Xiaochun Li, Kenta Yuyama, Hiroe Fujita, Shodai Sakurada, Yuki Uemura, Yuji Hatano, Naoaki Yoshida, Naoko Ashikawa, Akio Sagara, Takumi Chikada

    Physica Scripta 2016 (T167) 2016/01/25

    DOI: 10.1088/0031-8949/T167/1/014037  

    ISSN: 0281-1847

  123. Effect of neutron energy and fluence on deuterium retention behaviour in neutron irradiated tungsten Peer-reviewed

    Hiroe Fujita, Kenta Yuyama, Xiaochun Li, Yuji Hatano, Takeshi Toyama, Masayuki Ohta, Kentaro Ochiai, Naoaki Yoshida, Takumi Chikada, Yasuhisa Oya

    Physica Scripta 2016 (T167) 2016/01/25

    DOI: 10.1088/0031-8949/T167/1/014068  

    ISSN: 0281-1847

  124. Tritium distributions on tungsten and carbon tiles used in the JET divertor Peer-reviewed

    Y. Hatano, K. Yumizuru, J. Likonen, S. Koivuranta, J. Ikonen

    Physica Scripta 2016 (T167) 2016/01/25

    DOI: 10.1088/0031-8949/T167/1/014009  

    ISSN: 0281-1847

  125. Tritium retention in individual metallic dust particles examined by a tritium imaging plate technique Peer-reviewed

    T. Otsuka, Y. Hatano

    Physica Scripta 2016 (T167) 2016/01/25

    DOI: 10.1088/0031-8949/T167/1/014010  

    ISSN: 0281-1847

  126. Tritium desorption and tritium removal from tungsten pre-irradiated with helium Peer-reviewed

    Yuji Nobuta, Yuji Hatano, Yuji Torikai, Masao Matsuyama, Shinsuke Abe, Yuji Yamauchi

    Fusion Engineering and Design 109-111 1179-1182 2016

    DOI: 10.1016/j.fusengdes.2015.12.059  

    ISSN: 0920-3796

    eISSN: 1873-7196

  127. Dynamics for HT and HTO recovery through water bubbler and CuO catalyst Peer-reviewed

    Yasuhisa Oya, Misaki Sato, Kenta Yuyama, Masanori Hara, Yuji Hatano, Masao Matsuyama, Takumi Chikada

    Fusion Science and Technology 68 (2) 358-361 2015/09/01

    DOI: 10.13182/FST14-931  

    ISSN: 1536-1055

  128. 2D tritium distribution on tungsten tiles used in JET ITER-like wall project Peer-reviewed

    Y. Hatano, A. Widdowson, N. Bekris, C. Ayres, A. Baron-Wiechec, J. Likonen, S. Koivuranta, J. Ikonen, K. Yumizuru

    Journal of Nuclear Materials 463 966-969 2015/07/22

    DOI: 10.1016/j.jnucmat.2014.12.041  

    ISSN: 0022-3115

  129. Influence of helium on hydrogen isotope exchange in tungsten at sequential exposures to deuterium and helium-protium plasmas Peer-reviewed

    N. P. Bobyr, V. Kh Alimov, B. I. Khripunov, A. V. Spitsyn, M. Mayer, Y. Hatano, A. V. Golubeva, V. B. Petrov

    Journal of Nuclear Materials 463 1122-1124 2015/07/22

    DOI: 10.1016/j.jnucmat.2014.12.022  

    ISSN: 0022-3115

  130. Helium irradiation effects on tritium retention and long-term tritium release properties in polycrystalline tungsten Peer-reviewed

    Y. Nobuta, Y. Hatano, M. Matsuyama, S. Abe, Y. Yamauchi, T. Hino

    Journal of Nuclear Materials 463 993-996 2015/07/22

    DOI: 10.1016/j.jnucmat.2014.12.047  

    ISSN: 0022-3115

  131. Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten Peer-reviewed

    C. N. Taylor, M. Shimada, B. J. Merrill, D. W. Akers, Y. Hatano

    Journal of Nuclear Materials 463 1009-1012 2015/07/22

    DOI: 10.1016/j.jnucmat.2014.11.033  

    ISSN: 0022-3115

  132. Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten Peer-reviewed

    Masashi Shimada, Masanori Hara, Teppei Otsuka, Yasuhisa Oya, Yuji Hatano

    Journal of Nuclear Materials 463 1005-1008 2015/07/22

    DOI: 10.1016/j.jnucmat.2014.10.054  

    ISSN: 0022-3115

    eISSN: 1873-4820

  133. Thermal desorption behavior of deuterium for 6 MeV Fe ion irradiated W with various damage concentrations Peer-reviewed

    Yasuhisa Oya, Xiaochun Li, Misaki Sato, Kenta Yuyama, Long Zhang, Sosuke Kondo, Tatsuya Hinoki, Yuji Hatano, Hideo Watanabe, Naoaki Yoshida, Takumi Chikada

    Journal of Nuclear Materials 461 336-340 2015/07

    DOI: 10.1016/j.jnucmat.2015.03.032  

    ISSN: 0022-3115

  134. Preheating temperature effect on tritium retention in VPS-W Peer-reviewed

    Misaki Sato, Hiromichi Uchimura, Kensuke Toda, Tomonori Tokunaga, Hideo Watanabe, Naoaki Yoshida, Yuji Hatano, Ryuta Kasada, Takuya Nagasaka, Akihiko Kimura, Yasuhisa Oya, Kenji Okuno

    Fusion Science and Technology 67 (3) 551-554 2015/04

    DOI: 10.13182/FST14-T77  

    ISSN: 1536-1055

  135. In-situ observation of sputtered particles for carbon implanted tungsten during energetic hydrogen isotope ion implantation Peer-reviewed

    Yasuhisa Oya, Misaki Sato, Hiromichi Uchimura, Naoko Ashikawa, Akio Sagara, Naoaki Yoshida, Yuji Hatano, Kenji Okuno

    Fusion Science and Technology 67 (3) 515-518 2015/04

    DOI: 10.13182/FST14-T68  

    ISSN: 1536-1055

    eISSN: 1943-7641

  136. Formation of α-alumina scales in the Fe-Al(Cr) diffusion coating on China low activation martensitic steel Peer-reviewed

    Qin Zhan, Weiwei Zhao, Hongguang Yang, Yuji Hatano, Xiaoming Yuan, Teo Nozaki, Xinxin Zhu

    Journal of Nuclear Materials 464 135-139 2015/04

    DOI: 10.1016/j.jnucmat.2015.04.038  

    ISSN: 0022-3115

    eISSN: 1873-4820

  137. Tritium retention in reduced-activation ferritic/martensitic steels Peer-reviewed

    Y. Hatano, V. Kh Alimov, A. V. Spitsyn, N. P. Bobyr, D. I. Cherkez, S. Abe, O. V. Ogorodnikova, N. S. Klimov, B. I. Khripunov, A. V. Golubeva, V. M. Chernov, M. Oyaidzu, T. Yamanishi, M. Matsuyama

    Fusion Science and Technology 67 (2) 361-364 2015/03/01

    DOI: 10.13182/FST14-T30  

    ISSN: 1536-1055

  138. Effect of hydrogen on fatigue crack propagation behavior of wrought magnesium alloy AZ61 in NaCl solution under controlled cathodic potentials Peer-reviewed

    Toshifumi Kakiuchi, Yoshihiko Uematsu, Yuji Hatano, Masaki Nakajima, Yuki Nakamura, Tomonori Taniguchi

    Engineering Fracture Mechanics 137 88-96 2015/03/01

    DOI: 10.1016/j.engfracmech.2015.03.032  

    ISSN: 0013-7944

  139. Thermodynamics of hydrogen-induced superabundant vacancy in tungsten Peer-reviewed

    Kazuhito Ohsawa, Fumihiro Nakamori, Yuji Hatano, Masatake Yamaguchi

    Journal of Nuclear Materials 458 187-197 2015/03

    DOI: 10.1016/j.jnucmat.2014.12.029  

    ISSN: 0022-3115

    eISSN: 1873-4820

  140. Irradiation effect on deuterium behaviour in low-dose HFIR neutron-irradiated tungsten Peer-reviewed

    Masashi Shimada, G. Cao, T. Otsuka, M. Hara, M. Kobayashi, Y. Oya, Y. Hatano

    Nuclear Fusion 55 (1) 2015/01/01

    DOI: 10.1088/0029-5515/55/1/013008  

    ISSN: 0029-5515

    eISSN: 1741-4326

  141. Comparison of hydrogen isotope retention for tungsten probes in LHD vacuum vessel during the experimental campaigns in 2011 and 2012 Peer-reviewed

    Y. Oya, S. Masuzaki, M. Tokitani, M. Sato, K. Toda, H. Uchimura, N. Yoshida, H. Watanabe, Y. Yamauchi, T. Hino, M. Miyamoto, Y. Hatano, K. Okuno

    Fusion Engineering and Design 89 (7-8) 1091-1095 2014/10

    DOI: 10.1016/j.fusengdes.2013.12.018  

    ISSN: 0920-3796

  142. Tritium retention properties of tungsten, graphite and co-deposited carbon film Peer-reviewed

    Y. Nobuta, Y. Hatano, M. Matsuyama, S. Abe, S. Akamaru, Y. Yamauchi, T. Hino, S. Suzuki, M. Akiba

    Fusion Engineering and Design 89 (7-8) 1516-1519 2014/10

    DOI: 10.1016/j.fusengdes.2014.04.004  

    ISSN: 0920-3796

  143. Surface morphology and deuterium retention in tungsten and tungsten-rhenium alloy exposed to low-energy, high flux D plasma Peer-reviewed

    V. Kh Alimov, Y. Hatano, K. Sugiyama, M. Balden, M. Oyaidzu, S. Akamaru, K. Tada, H. Kurishita, T. Hayashi, M. Matsuyama

    Journal of Nuclear Materials 454 (1-3) 136-141 2014/08/19

    DOI: 10.1016/j.jnucmat.2014.07.064  

    ISSN: 0022-3115

  144. Current activities in the interactive joint research at tohoku university - advanced evaluation of radiation effects on fusion materials Peer-reviewed

    Hiroaki Kurishita, Masahiko Hatakeyama, Minoru Narui, Satoru Matsuo, Tatsuo Shikama, Kohei Tada, Noriyasu Ohno, Takao Takeuchi, Yuji Hatano, Masaki Nishiura, Yousuke Nakashima, Hideo Watanabe, Kazutoshi Tokunaga, Tomoaki Hino, Yoshio Ueda, Takeo Muroga, Akio Sagara, Osamu Kaneko

    Plasma and Fusion Research 9 (SpecialIssue2) 2014

    DOI: 10.1585/pfr.9.3405136  

    eISSN: 1880-6821

  145. Current status of nanostructured tungsten-based materials development Peer-reviewed

    H. Kurishita, S. Matsuo, H. Arakawa, T. Sakamoto, S. Kobayashi, K. Nakai, H. Okano, H. Watanabe, N. Yoshida, Y. Torikai, Y. Hatano, T. Takida, M. Kato, A. Ikegaya, Y. Ueda, M. Hatakeyama, T. Shikama

    Physica Scripta T159 2014

    DOI: 10.1088/0031-8949/2014/T159/014032  

    ISSN: 0281-1847

  146. Development of positron annihilation spectroscopy for characterizing neutron irradiated tungsten Peer-reviewed

    C. N. Taylor, M. Shimada, B. J. Merrill, M. W. Drigert, D. W. Akers, Y. Hatano

    Physica Scripta T159 2014

    DOI: 10.1088/0031-8949/2014/T159/014055  

    ISSN: 0281-1847

  147. Influence of tungsten-carbon mixed layer and irradiation defects on deuterium retention behavior in tungsten Peer-reviewed

    Ryo Miura, Tetsuo Fujishima, Hiromichi Uchimura, Kensuke Toda, Makoto Kobayashi, Naoko Ashikawa, Akio Sagara, Naoaki Yoshida, Yuji Hatano, Yasuhisa Oya, Kenji Okuno

    Fusion Engineering and Design 88 (9-10) 1827-1830 2013/10

    DOI: 10.1016/j.fusengdes.2013.04.051  

    ISSN: 0920-3796

  148. Enhancement of hydrogen isotope retention capacity for the impurity deposited tungsten by long-term plasma exposure in LHD Peer-reviewed

    Yasuhisa Oya, Suguru Masuzaki, Masayuki Tokitani, Naoaki Yoshida, Hideo Watanabe, Yuji Yamauchi, Tomoaki Hino, Mitsutaka Miyamoto, Yuji Hatano, Kenji Okuno

    Fusion Engineering and Design 88 (9-10) 1699-1703 2013/10

    DOI: 10.1016/j.fusengdes.2013.03.002  

    ISSN: 0920-3796

  149. Deuterium trapping by irradiation damage in tungsten induced by different displacement processes Peer-reviewed

    Makoto Kobayashi, Masashi Shimada, Yuji Hatano, Takuji Oda, Brad Merrill, Yasuhisa Oya, Kenji Okuno

    Fusion Engineering and Design 88 (9-10) 1749-1752 2013/10

    DOI: 10.1016/j.fusengdes.2013.04.009  

    ISSN: 0920-3796

  150. Hydrogen permeation through a Pd/Ta composite membrane with a HfN intermediate layer Peer-reviewed

    T. Nozaki, Y. Hatano

    International Journal of Hydrogen Energy 38 (27) 11983-11987 2013/09/10

    DOI: 10.1016/j.ijhydene.2013.07.012  

    ISSN: 0360-3199

  151. Tritium interaction with surface layer and bulk of type 316 stainless steel and consequences of aging Peer-reviewed

    R. D. Penzhorn, Y. Hatano, M. Matsuyama, Y. Torikai

    Fusion Science and Technology 64 (1) 45-53 2013/07

    DOI: 10.13182/FST12-625  

    ISSN: 1536-1055

  152. Deuterium Retention Properties of Co-Deposited Carbon Films Produced at Wall Gaps

    NOBUTA Yuji, KANAZAWA Jun, YAMAUCHI Yuji, HINO Tomoaki, YOKOYAMA Kenji, SUZUKI Satoshi, EZATO Koichiro, ENOEDA Mikio, AKIBA Masato, AKAMARU Satoshi, HATANO Yuji

    Plasma and Fusion Research 8 2405174-2405174 2013

    Publisher: The Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.8.2405174  

    ISSN: 1880-6821

    More details Close

    Deuterium retention properties in co-deposited carbon film produced in gap and the relationship between this retention behavior and the crystal structure of carbon film were investigated. In the case of a wide gap, the atomic ratio of deuterium to carbon (D/C) in the film was almost constant at any depth in the gap, while in the case of a narrow gap the D/C ratio decreased with increasing distance from the gap entrance. The micro structure of carbon film tended to be more amorphous for the film produced at locations deeper in the gap. Thermal desorption spectra of D2 in the film produced near the gap entrance showed one broad main peak at around 1100 K, while that in the film produced near the bottom showed very sharp peaks at around 950 K. This difference in desorption behavior was related with the differences of micro structure.

  153. The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D<inf>2</inf> gas Peer-reviewed

    V. Kh Alimov, Y. Hatano, K. Sugiyama, J. Roth, B. Tyburska-Püschel, J. Dorner, J. Shi, M. Matsuyama, K. Isobe, T. Yamanishi

    Journal of Nuclear Materials 438 (SUPPL) 2013

    DOI: 10.1016/j.jnucmat.2013.01.208  

    ISSN: 0022-3115

  154. In situ observation of deuterium trapping in self-ion irradiated tungsten Peer-reviewed

    Ikuji Takagi, Kazuyoshi Yamamichi, Yoshinori Furuta, Masafumi Akiyoshi, Takayuki Sasaki, Hidetsugu Tsuchida, Yuji Hatano

    Journal of Nuclear Materials 442 (1-3 SUPPL.1) S246 2013

    DOI: 10.1016/j.jnucmat.2013.04.030  

    ISSN: 0022-3115

  155. Tritium trapping in silicon carbide in contact with solid breeder under high flux isotope reactor irradiation Peer-reviewed

    H. Katsui, Y. Katoh, A. Hasegawa, M. Shimada, Y. Hatano, T. Hinoki, S. Nogami, T. Tanaka, S. Nagata, T. Shikama

    Journal of Nuclear Materials 442 (1-3 SUPPL.1) 2013

    DOI: 10.1016/j.jnucmat.2012.12.021  

    ISSN: 0022-3115

  156. Behaviors of deuterium retention and microstructure change of tungsten simultaneously implanted with carbon and/or helium ions

    Yasuhisa Oya, Makoto Kobayashi, Tetsuo Fujishima, Kiyotaka Kawasaki, Yuto Miyahara, Naoaki Yoshida, Yuji Hatano, Naoko Ashikawa, Akio Sagara, Kenji Okuno

    Materials Transactions 54 (4) 430-436 2013

    DOI: 10.2320/matertrans.MG201205  

    ISSN: 1345-9678

  157. Study on kinetics of hydrogen dissolution and hydrogen solubility in oxides using imaging plate technique Peer-reviewed

    K. Hashizume, K. Ogata, M. Nishikawa, T. Tanabe, S. Abe, S. Akamaru, Y. Hatano

    Journal of Nuclear Materials 442 (1-3 SUPPL.1) 2013

    DOI: 10.1016/j.jnucmat.2013.05.038  

    ISSN: 0022-3115

  158. Analysis of a tritium enhanced water spectrum between 7200 and 7245 cm -1 using new variational calculations Peer-reviewed

    Michael J. Down, Jonathan Tennyson, Masanori Hara, Yuji Hatano, Kaori Kobayashi

    Journal of Molecular Spectroscopy 289 35-40 2013

    DOI: 10.1016/j.jms.2013.05.016  

    ISSN: 0022-2852

    eISSN: 1096-083X

  159. Tritium Autoradiography Study on Hydrogen Invading Aluminum from Different Environments

    Watakabe Takahito, Itoh Goroh, Hatano Yuji

    Journal of the Japan Institute of Metals and Materials 77 (12) 565-570 2013

    Publisher: The Japan Institute of Metals and Materials

    DOI: 10.2320/jinstmet.JC201317  

    ISSN: 0021-4876

  160. OS1512 Fatigue crack propagation behaviour of AZ61 magnesium alloy under controlled cathodic potential

    TANIGUCHI Tomonori, UEMATSU Yoshihiko, HATANO Yuji, KAKIUCHI Toshifumi, NAKAJIMA Masaki, NAKAMURA Yuki

    The Proceedings of the Materials and Mechanics Conference 2013 (0) _OS1512-1_-_OS1512-3_ 2013

    Publisher: The Japan Society of Mechanical Engineers

    DOI: 10.1299/jsmemm.2013._OS1512-1_  

    ISSN: 1022-6680

  161. Retention and desorption behavior of tritium in Si related ceramics Peer-reviewed

    Yasuhisa Oya, Yuji Hatano, Masanori Hara, Masao Matsuyama, Kenji Okuno

    Journal of Nuclear Materials 438 (1-3) 22-25 2013

    DOI: 10.1016/j.jnucmat.2013.03.001  

    ISSN: 0022-3115

  162. Enhancement of hydrogen isotope retention in tungsten exposed to LHD plasmas Peer-reviewed

    Yasuhisa Oya, Suguru Masuzaki, Tetsuo Fujishima, Masayuki Tokitani, Naoaki Yoshida, Hideo Watanabe, Yuji Yamauchi, Tomoaki Hino, Mitsutaka Miyamoto, Yuji Hatano, Kenji Okuno

    Journal of Nuclear Materials 438 (SUPPL) S1055-S1058 2013

    DOI: 10.1016/j.jnucmat.2013.01.231  

    ISSN: 0022-3115

    eISSN: 1873-4820

  163. Behavior of deuterium retention and surface morphology for VPS-W/F82H Peer-reviewed

    Yasuhisa Oya, Masashi Shimada, Tomonori Tokunaga, Hideo Watanabe, Naoaki Yoshida, Yuji Hatano, Ryuta Kasada, Takuya Nagasaka, Akihiko Kimura, Kenji Okuno

    Journal of Nuclear Materials 442 (1-3 SUPPL.1) S242-S245 2013

    DOI: 10.1016/j.jnucmat.2013.01.321  

    ISSN: 0022-3115

    eISSN: 1873-4820

  164. Tritium retention in nanostructured tungsten with large effective surface area Peer-reviewed

    Miyuki Yajima, Yuji Hatano, Shin Kajita, Jie Shi, Masanori Hara, Noriyasu Ohno

    Journal of Nuclear Materials 438 (SUPPL) S1142-S1145 2013

    DOI: 10.1016/j.jnucmat.2013.01.252  

    ISSN: 0022-3115

  165. Dynamic deuterium recycling on tungsten under carbon-deuterium implantation circumstance Peer-reviewed

    Tomohisa Taguchi, Makoto Kobayashi, Kiyotaka Kawasaki, Yuto Miyahara, Naoko Ashikawa, Akio Sagara, Naoaki Yoshida, Mitsutaka Miyamoto, Kotaro Ono, Yuji Hatano, Yasuhisa Oya, Kenji Okuno

    Journal of Nuclear Materials 438 (SUPPL) S1117-S1120 2013

    DOI: 10.1016/j.jnucmat.2013.01.246  

    ISSN: 0022-3115

    eISSN: 1873-4820

  166. Self-hardening effect of CrAlN/BN nanocomposite films deposited by direct current and radio frequency reactive cosputtering Peer-reviewed

    Masateru Nose, Wen An Chiou, Tokimasa Kawabata, Yuji Hatano, Kenji Matsuda

    Thin Solid Films 523 6-10 2012/11/15

    DOI: 10.1016/j.tsf.2012.05.063  

    ISSN: 0040-6090

  167. Overview of the US-Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten Peer-reviewed

    Masashi Shimada, Y. Hatano, Y. Oya, T. Oda, M. Hara, G. Cao, M. Kobayashi, M. Sokolov, H. Watanabe, B. Tyburska-Püschel, Y. Ueda, P. Calderoni, K. Okuno

    Fusion Engineering and Design 87 (7-8) 1166-1170 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.103  

    ISSN: 0920-3796

  168. Effect of hydrophobic paints coating for tritium reduction in concrete materials Peer-reviewed

    Y. Edao, S. Fukada, Y. Nishimura, K. Katayama, T. Takeishi, Y. Hatano, A. Taguchi

    Fusion Engineering and Design 87 (7-8) 995-998 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.058  

    ISSN: 0920-3796

  169. Study on the retention behavior of hydrogen isotopes and the change of chemical states of boron film exposed to hydrogen plasma in LHD Peer-reviewed

    Akiko Hamada, Makoto Kobayashi, Katsushi Matsuoka, Masato Suzuki, Junya Osuo, Naoko Ashikawa, Akio Sagara, Yuji Hatano, Yasuhisa Oya, Kenji Okuno

    Fusion Engineering and Design 87 (7-8) 1214-1217 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.112  

    ISSN: 0920-3796

  170. Measurement of deuterium and helium by glow-discharge optical emission spectroscopy for plasma-surface interaction studies Peer-reviewed

    Yuji Hatano, Jie Shi, Naoaki Yoshida, Naoki Futagami, Yasuhisa Oya, Hirofumi Nakamura

    Fusion Engineering and Design 87 (7-8) 1091-1094 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.078  

    ISSN: 0920-3796

  171. Deuterium behavior at the interface of oxidized metal under high temperature heavy water Peer-reviewed

    Hirofumi Nakamura, Yuji Hatano, Toshihiko Yamanishi

    Fusion Engineering and Design 87 (5-6) 916-920 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.044  

    ISSN: 0920-3796

  172. Tritium depth profile in matter using an imaging plate Peer-reviewed

    Hiroko Ohuchi-Yoshida, Yuji Hatano, Yasushi Kino, Yasuhiro Kondo

    Fusion Engineering and Design 87 (5-6) 423-426 2012/08

    DOI: 10.1016/j.fusengdes.2011.11.012  

    ISSN: 0920-3796

  173. Tritium absorption of co-deposited carbon films Peer-reviewed

    Yuji Nobuta, Yuji Yamauchi, Tomoaki Hino, Satoshi Akamaru, Yuji Hatano, Masao Matsuyama, Satoshi Suzuki, Masato Akiba

    Fusion Engineering and Design 87 (7-8) 1070-1073 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.080  

    ISSN: 0920-3796

    eISSN: 1873-7196

  174. Measurement of tritium concentration in water by imaging plate Peer-reviewed

    Yuji Hatano, Masanori Hara, Hiroko Ohuchi-Yoshida, Hirofumi Nakamura, Toshihiko Yamanishi

    Fusion Engineering and Design 87 (7-8) 965-968 2012/08

    DOI: 10.1016/j.fusengdes.2012.02.057  

    ISSN: 0920-3796

  175. Effect of surface oxide layer on deuterium permeation behaviors through a type 316 stainless steel Peer-reviewed

    Yasuhisa Oya, Makoto Kobayashi, Junya Osuo, Masato Suzuki, Akiko Hamada, Katsushi Matsuoka, Yuji Hatano, Masao Matsuyama, Takumi Hayashi, Toshihiko Yamanishi, Kenji Okuno

    Fusion Engineering and Design 87 (5-6) 580-583 2012/08

    DOI: 10.1016/j.fusengdes.2012.01.025  

    ISSN: 0920-3796

  176. Permeation measurements for investigating atomic hydrogen flux and wall pumping/fuelling dynamics in QUEST Peer-reviewed

    S. K. Sharma, H. Zushi, I. Takagi, Y. Hisano, T. Shikama, S. Morita, T. Tanabe, N. Yoshida, M. Sakamoto, Y. Higashizono, K. Hanada, M. Hasegawa, K. Nakamura, H. Idei, K. N. Sato, S. Kawasaki, H. Nakashima, A. Higashijima, Y. Nakashima, Y. Hatano, A. Sagara, Y. Nakamura, N. Ashikawa, T. Maekawa, Y. Kishimoto, Y. Takase

    Journal of Nuclear Materials 420 (1-3) 83-93 2012/01

    DOI: 10.1016/j.jnucmat.2011.09.026  

    ISSN: 0022-3115

  177. Transfer of tritium in concrete coated with hydrophobic paints Peer-reviewed

    S. Fukada, Y. Edao, K. Sato, T. Takeishi, K. Katayama, K. Kobayashi, T. Hayashi, T. Yamanishi, Y. Hatano, A. Taguchi, S. Akamaru

    Fusion Engineering and Design 87 (1) 54-60 2012/01

    DOI: 10.1016/j.fusengdes.2011.09.001  

    ISSN: 0920-3796

  178. Behavior of hydrogen invasion in aluminum alloys from different environments Peer-reviewed

    Takahito Watakabe, Goroh Itoh, Yuji Hatano

    Advanced Materials Research 409 92-95 2012

    DOI: 10.4028/www.scientific.net/AMR.409.92  

    ISSN: 1022-6680

  179. Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma Peer-reviewed

    V. Kh Alimov, B. Tyburska-Püschel, S. Lindig, Y. Hatano, M. Balden, J. Roth, K. Isobe, M. Matsuyama, T. Yamanishi

    Journal of Nuclear Materials 420 (1-3) 519-524 2012/01

    DOI: 10.1016/j.jnucmat.2011.11.003  

    ISSN: 0022-3115

  180. The effect of displacement damage on deuterium retention in ITER-grade tungsten exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas Peer-reviewed

    V. Kh Alimov, B. Tyburska-Püschel, Y. Hatano, J. Roth, K. Isobe, M. Matsuyama, T. Yamanishi

    Journal of Nuclear Materials 420 (1-3) 370-373 2012/01

    DOI: 10.1016/j.jnucmat.2011.10.025  

    ISSN: 0022-3115

  181. Oxidation resistance and self hardening of CrAlN/BN nanocomposite coatings Peer-reviewed

    Masateru Nose, Tomohiro Watanuki, Tokimasa Kawabata, Yuji Hatano, Kenji Matsuda, Ssusumu Ikeno

    Materials Science Forum 706-709 2559-2564 2012

    DOI: 10.4028/www.scientific.net/MSF.706-709.2559  

    ISSN: 0255-5476

    eISSN: 1662-9752

  182. Recent progress of tungsten R&D for fusion application in Japan Peer-reviewed

    Y. Ueda, H. T. Lee, N. Ohno, S. Kajita, A. Kimura, R. Kasada, T. Nagasaka, Y. Hatano, A. Hasegawa, H. Kurishita, Y. Oya

    PHYSICA SCRIPTA T145 14029 2011/12

    DOI: 10.1088/0031-8949/2011/T145/014029  

    ISSN: 0031-8949

    eISSN: 1402-4896

  183. Fabrication of ZrO2 coatings on ferritic steel by wet-chemical methods as a tritium permeation barrier Peer-reviewed

    Y. Hatano, K. Zhang, K. Hashizume

    PHYSICA SCRIPTA T145 2011/12

    DOI: 10.1088/0031-8949/2011/T145/014044  

    ISSN: 0031-8949

  184. Hydrogen permeation measurements in the spherical tokamak quest and its numerical modeling Peer-reviewed

    S. K. Sharma, H. Zushi, I. Takagi, Y. Hisano, T. Shikama, S. Morita, T. Tanabe, N. Yoshida, M. Sakamoto, Y. Higashizono, K. Hanada, M. Hasegawa, O. Mitarai, K. Nakamura, H. Idei, K. N. Sato, S. Kawasaki, H. Nakashima, A. Higashijima, Y. Nakashima, N. Nishino, Y. Hatano, A. Sagara, Y. Nakamura, N. Ashikawa, T. Maekawa, Y. Kishimoto, Y. Takase

    Fusion Science and Technology 60 (4) 1511-1514 2011/11

    DOI: 10.13182/FST11-A12719  

    ISSN: 1536-1055

  185. Development of monte carlo simulation code to model behavior of hydrogen isotopes loaded into tungsten containig vacancies Peer-reviewed

    T. Oda, M. Shimada, K. Zhang, P. Calderoni, Y. Oya, M. Sokolov, R. Kolasinski, J. P. Sharpe, Y. Hatano

    Fusion Science and Technology 60 (4) 1455-1458 2011/11

    DOI: 10.13182/fst11-a12705  

    ISSN: 1536-1055

  186. Tritium absorption of co-deposited carbon films, graphite and polycrystalline tungsten Peer-reviewed

    Y. Nobuta, Y. Yamauchi, T. Hino, S. Akamaru, Y. Hatano, M. Matsuyama, S. Suzuki, M. Akiba

    Fusion Science and Technology 60 (4) 1535-1538 2011/11

    DOI: 10.13182/fst11-a12725  

    ISSN: 1536-1055

  187. Influence of Chromium oxide layer on surface tritium contamination of type 316 stainless steel Peer-reviewed

    Yohei Ozeki, Yuji Hatano, Haruka Taniguchi, Masao Matsuyama

    Fusion Science and Technology 60 (4) 1499-1502 2011/11

    DOI: 10.13182/FST11-A12716  

    ISSN: 1536-1055

  188. Tritium transfer in porous concrete materials coated with hydrophobic paints Peer-reviewed

    S. Fukada, Y. Edao, K. Sato, T. Takeishi, K. Katayama, K. Kobayashi, T. Hayashi, T. Yamanishi, Y. Hatano, A. Taguchi, S. Akamaru

    Fusion Science and Technology 60 (3) 1061-1064 2011/10

    DOI: 10.13182/FST11-A12599  

    ISSN: 1536-1055

  189. Trapping and depth profile of tritium in surface layers of metallic materials Peer-reviewed

    M. Matsuyama, Z. Chen, K. Nisimura, S. Akamaru, Y. Torikai, Y. Hatano, N. Ashikawa, Y. Oya, K. Okuno, T. Hino

    Journal of Nuclear Materials 417 (1-3) 900-903 2011/10/01

    DOI: 10.1016/j.jnucmat.2011.04.005  

    ISSN: 0022-3115

  190. Near-infrared spectroscopy of tritiated water Peer-reviewed

    Kaori Kobayashi, Tomoya Enokida, Daisuke Lio, Yuta Yamada, Masanori Hara, Yuji Hatano

    Fusion Science and Technology 60 (3) 941-943 2011/10

    Publisher: American Nuclear Society

    DOI: 10.13182/FST11-A12570  

    ISSN: 1536-1055

  191. Measurement of highly tritiated water by imaging plate Peer-reviewed

    Yuji Hatano, Masanori Hara, Hiroko Ohuchi, Hirofumi Nakamura, Takumi Hayashi, Toshihiko Yamanishi

    Fusion Science and Technology 60 (3) 982-985 2011/10

    Publisher: American Nuclear Society

    DOI: 10.13182/FST11-A12580  

    ISSN: 1536-1055

  192. Comparison of hydrogen isotope retention and irradiation damage behaviors in tungsten and SS-316 with simultaneous C+-D<inf>2</inf>+ implantation Peer-reviewed

    Yasuhisa Oya, Makoto Kobayashi, Rie Kurata, Naoaki Yoshida, Naoko Ashikawa, Akio Sagara, Masanori Hara, Yuji Hatano, Kenji Okuno

    Fusion Engineering and Design 86 (9-11) 1776-1779 2011/10

    DOI: 10.1016/j.fusengdes.2010.11.017  

    ISSN: 0920-3796

  193. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility Peer-reviewed

    P. Calderoni, J. Sharpe, M. Shimada, B. Denny, B. Pawelko, S. Schuetz, G. Longhurst, Y. Hatano, M. Hara, Y. Oya, T. Otsuka, K. Katayama, S. Konishi, K. Noborio, Y. Yamamoto

    Journal of Nuclear Materials 417 (1-3) 1336-1340 2011/10/01

    DOI: 10.1016/j.jnucmat.2010.12.303  

    ISSN: 0022-3115

  194. Sealing of pores in sol-gel-derived tritium permeation barrier coating by electrochemical technique Peer-reviewed

    Kun Zhang, Yuji Hatano

    Journal of Nuclear Materials 417 (1-3) 1229-1232 2011/10/01

    DOI: 10.1016/j.jnucmat.2010.12.276  

    ISSN: 0022-3115

  195. Temperature dependence of retention of energetic deuterium and carbon simultaneously implanted into tungsten Peer-reviewed

    Wanjing Wang, Makoto Kobayashi, Rie Kurata, Sachiko Suzuki, Naoko Ashikawa, Akio Sagara, Naoaki Yoshida, Yuji Hatano, Guang Nan Luo, Yasuhisa Oya, Kenji Okuno

    Journal of Nuclear Materials 417 (1-3) 555-558 2011/10/01

    DOI: 10.1016/j.jnucmat.2010.12.111  

    ISSN: 0022-3115

  196. First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE Peer-reviewed

    Masashi Shimada, Y. Hatano, P. Calderoni, T. Oda, Y. Oya, M. Sokolov, K. Zhang, G. Cao, R. Kolasinski, J. P. Sharpe

    Journal of Nuclear Materials 415 (1 SUPPL) 2011/08/01

    DOI: 10.1016/j.jnucmat.2010.11.050  

    ISSN: 0022-3115

  197. Application of tritium imaging plate technique to examine tritium behaviors on the surface and in the bulk of plasma-exposed materials Peer-reviewed

    T. Otsuka, M. Shimada, R. Kolasinski, P. Calderoni, J. P. Sharpe, Y. Ueda, Y. Hatano, T. Tanabe

    Journal of Nuclear Materials 415 (1 SUPPL) 2011/08/01

    DOI: 10.1016/j.jnucmat.2010.11.046  

    ISSN: 0022-3115

  198. Hydrogen permeation and recombination in Ni membrane placed on spherical tokamak QUEST Peer-reviewed

    I. Takagi, S. K. Sharma, H. Zushi, R. Imade, T. Komura, Y. Hisano, Y. Hatano, Y. Nakamura, A. Sagara, N. Ashikawa

    Journal of Nuclear Materials 415 (1 SUPPL) S692-S695 2011/08/01

    DOI: 10.1016/j.jnucmat.2010.12.011  

    ISSN: 0022-3115

  199. Dynamics of hydrogen isotope trapping and detrapping for tungsten under simultaneous triple ion (C+, D 2 + and He+) implantation Peer-reviewed

    Yasuhisa Oya, Makoto Kobayashi, Rie Kurata, Wanjing Wang, Naoko Ashikawa, Akio Sagara, Naoaki Yoshida, Yuji Hatano, Kenji Okuno

    Journal of Nuclear Materials 415 (1 SUPPL) S701-S704 2011/08/01

    DOI: 10.1016/j.jnucmat.2010.09.058  

    ISSN: 0022-3115

  200. Pressure-composition isotherms of TiC<inf>1-x</inf>-H system at elevated temperatures Peer-reviewed

    Teo Nozaki, Hirofumi Homma, Yuji Hatano

    Materials Transactions 52 (3) 526-530 2011/03

    DOI: 10.2320/matertrans.M2010307  

    ISSN: 1345-9678

    eISSN: 1347-5320

  201. Midterm summary of Japan-US fusion cooperation program TITAN Peer-reviewed

    T. Muroga, D. K. Sze, K. Okuno, T. Terai, A. Kimura, R. J. Kurtz, A. Sagara, R. Nygren, Y. Ueda, R. P. Doerner, J. P. Sharpe, T. Kunugi, N. B. Morley, Y. Hatano, M. A. Sokolov, T. Yamamoto, A. Hasegawa, Y. Katoh, N. Ohno, K. Tokunaga, S. Konishi, S. Fukada, P. Calderoni, T. Yokomine, K. Messadek, Y. Oya, N. Hashimoto, T. Hinoki, H. Hashizume, T. Norimatsu, T. Shikama, R. E. Stoller, K. A. Tanaka, M. S. Tillack

    Fusion Science and Technology 60 (1) 321-328 2011

    DOI: 10.13182/FST11-A12373  

    ISSN: 1536-1055

    eISSN: 1943-7641

  202. Study on compatibility between silicon carbide and solid breeding materials under neutron irradiation Peer-reviewed

    H. Katsui, A. Hasegawa, Y. Katoh, Y. Hatano, T. Tanaka, S. Nogami, T. Hinoki, T. Shikama

    Fusion Science and Technology 60 (1) 288-291 2011

    DOI: 10.13182/FST11-A12367  

    ISSN: 1536-1055

    eISSN: 1943-7641

  203. Recent progress of tungsten R&amp;D for fusion application in Japan Peer-reviewed

    Y. Ueda, H. T. Lee, N. Ohno, S. Kajita, A. Kimura, R. Kasada, T. Nagasaka, Y. Hatano, A. Hasegawa, H. Kurishita, Y. Oya

    Physica Scripta T T145 2011

    DOI: 10.1088/0031-8949/2011/T145/014029  

    ISSN: 0281-1847

  204. Comparison of deuterium retention for ion-irradiated or neutron-irradiated tungsten

    Oya Yasuhisa, Shimada Masashi, Oda Takuji, Hara Masanori, Hatano Yuji, Pattrick Calderoni, Okuno Kenji

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2011 (0) 720-720 2011

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2011s.0.720.0  

    ISSN: 0281-1847

  205. Fabrication of ZrO <inf>2</inf> coatings on ferritic steel by wet-chemical methods as a tritium permeation barrier Peer-reviewed

    Y. Hatano, K. Zhang, K. Hashizume

    Physica Scripta T T145 2011

    DOI: 10.1088/0031-8949/2011/T145/014044  

    ISSN: 0281-1847

  206. Hydrogen isotope exchange in tungsten irradiated sequentially with low-energy deuterium and protium ions Peer-reviewed

    V. Kh Alimov, B. Tyburska-Püschel, M. H.J. 'T Hoen, J. Roth, Y. Hatano, K. Isobe, M. Matsuyama, T. Yamanishi

    Physica Scripta T T145 2011

    DOI: 10.1088/0031-8949/2011/T145/014037  

    ISSN: 0281-1847

  207. The deuterium depth profile in neutron-irradiated tungsten exposed to plasma Peer-reviewed

    Masashi Shimada, G. Cao, Y. Hatano, T. Oda, Y. Oya, M. Hara, P. Calderoni

    Physica Scripta T T145 2011

    DOI: 10.1088/0031-8949/2011/T145/014051  

    ISSN: 0281-1847

  208. Preparation of Mg and Al phosphate coatings on ferritic steel by wet-chemical method as tritium permeation barrier Peer-reviewed

    Kun Zhang, Yuji Hatano

    Fusion Engineering and Design 85 (7-9) 1090-1093 2010/12

    DOI: 10.1016/j.fusengdes.2010.02.012  

    ISSN: 0920-3796

  209. Measurement of hydrogen permeation due to atomic flux using permeation probe in the spherical tokamak QUEST Peer-reviewed

    Sanjeev K. Sharma, Hideki Zushi, Ikuji Takagi, Yuki Hisano, Mizuki Sakamoto, Yuta Higashizono, Taichi Shikama, Sigeru Morita, Tetsuo Tanabe, Naoaki Yoshida, Kazuaki Hanada, Makoto Hasegawa, Osamu Mitarai, Kazuo Nakamura, Hiroshi Idei, Kohnosuke N. Sato, Shoji Kawasaki, Hisatoshi Nakashima, Aki Higashijima, Yousuke Nakashima, Nobuyuki Nishino, Yuji Hatano, Akira Sagara, Yukio Nakamura, Naoko Ashikawa, Takashi Maekawa, Yasuaki Kishimoto, Yuichi Takase

    Fusion Engineering and Design 85 (6) 950-955 2010/11

    DOI: 10.1016/j.fusengdes.2010.08.032  

    ISSN: 0920-3796

  210. Improvement of high temperature stability of Pd coating on Ta by HfN intermediate layer Peer-reviewed

    Teo Nozaki, Yuji Hatano, Eriko Yamakawa, Asuka Hachikawa, Kazuyoshi Ichinose

    International Journal of Hydrogen Energy 35 (22) 12454-12460 2010/11

    DOI: 10.1016/j.ijhydene.2010.08.114  

    ISSN: 0360-3199

  211. Hydrogen permeation through the Pd-V/Nb-Pd composite membranes: Surface effects and thermal degradation Peer-reviewed

    V. Alimov, Y. Hatano, A. Busnyuk, M. Notkin, A. Livshits

    20th Annual Meeting of the North American Membrane Society and 11th International Conference on Inorganic Membranes 2010, NAMS/ICIM 2010 36 (13) 60-61 2010

    DOI: 10.1016/j.ijhydene.2011.04.016  

    ISSN: 0360-3199

  212. Visualization of diffusive hydrogen Peer-reviewed

    Takahito Watakabe, Goroh Itoh, Yuji Hatano

    Materials Science Forum 654-656 2903-2906 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2903  

    ISSN: 0255-5476

    eISSN: 1662-9752

  213. Correlation between hydrogen distribution in V-4Cr-4Ti alloy and impact strength Peer-reviewed

    Y. Hatano, H. Homma, T. Sakamura, H. Saitoh, T. Nagasaka, T. Muroga, M. Matsuyama

    Journal of Nuclear Materials 386-388 (C) 569-571 2009/04

    DOI: 10.1016/j.jnucmat.2008.12.178  

    ISSN: 0022-3115

  214. Preliminary Study of H₂O Adsorption on Cr₂O₃ and Al₂O₃ Surfaces by Ab Initio Cluster Calculations

    Watanabe K., Torikai Y., Hara M., Hatano Y.

    富山大学水素同位体科学研究センター研究報告 = Annual Report of Hydrogen Isotope Research Center, University of Toyama 28 9-22 2009/03

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006510  

    ISSN: 1346-3675

    More details Close

    Adsorption and desorption of water over Cr-oxide and alumina are of great concern with the contamination of stainless steel and gas chromatographic isotope separation. However,the mechanisms of those phenomena have not been fully clarified. A preliminary ab inito study on the behavior of water molecules on the (001) surfaces of α-Cr₂O₃ and α-Al₂O₃ was carried out for small clusters of Me4O4 (Me=Cr or Al) by use of the Gaussian 03 package. It was found that water molecules can be adsorbed molecularly and dissociatively on these surfaces. Molecular adsorption of a H₂O molecule takes place on a metal atom of the cluster as Me-OH₂, with the bond length of about 2.0 Å. Dissociative adsorption occurs by forming Me-OH (on-top site) or Me2-OH (bridge site) and O-H bonds. There appeared a feature that the bond length of Me2-OH is greater than that of Me-OH. Calculated adsorption energies were examined by comparing with the values estimated from the thermal desorption spectra of water for α-Cr₂O₃ and γ-alumina. The ab initio calculations coincided quite well with the observed thermal desorption spectrum for α-Cr₂O₃, whereas they did not for γ-alumina. Further studies are required to clarify the structures of adsorbed species, adsorptiron energies and kinetic processes.

  215. Tritium diffusion in V4Cr-4Ti alloy Peer-reviewed

    K. Hashizume, J. Masuda, K. T. Otsuka, T. Tanabe, Y. Hatano, Y. Nakamura, T. Nagasaka, T. Muroga

    Fusion Science and Technology 54 (2) 553-556 2008/08

    DOI: 10.13182/FST08-A1876  

    ISSN: 1536-1055

  216. Influence of oxygen on permeation of hydrogen isotopes through group 5 metals Peer-reviewed

    Yuji Hatano, Andrei Busnyuk, Vasily Alimov, Alexander Livshits, Yukio Nakamura, Masao Matsuyama

    Fusion Science and Technology 54 (2) 526-529 2008/08

    DOI: 10.13182/FST08-A1869  

    ISSN: 1536-1055

  217. Correlation between hydrogen isotope permeation through niobium and bulk oxygen concentration: Possible influence of oxygen on tritium recovery from Pb-Li by vacuum permeator Peer-reviewed

    Yuji Hatano, Andrei Busnyuk, Alexander Livshits, Hirofumi Homma, Masao Matsuyama

    Fusion Science and Technology 52 (4) 990-994 2007/11

    DOI: 10.13182/FST07-A1623  

    ISSN: 1536-1055

  218. Improvement of high temperature stability of Pd coating on Nb by intermediate layer comprising NbC and Nb<inf>2</inf>C Peer-reviewed

    Yuji Hatano, Keita Ishiyama, Hirofumi Homma, Kuniaki Watanabe

    Journal of Alloys and Compounds 446-447 539-542 2007/10/31

    DOI: 10.1016/j.jallcom.2007.01.101  

    ISSN: 0925-8388

  219. Absorption of atomic hydrogen by vanadium Peer-reviewed

    Yuji Hatano, Andrei Busnyuk, Alexander Livshits, Yukio Nakamura, Masao Matsuyama

    Fusion Science and Technology 52 (3) 613-617 2007/10

    DOI: 10.13182/FST07-A1556  

    ISSN: 1536-1055

  220. Recent results on beryllium and beryllides in Japan Peer-reviewed

    Y. Mishima, N. Yoshida, H. Kawamura, K. Ishida, Y. Hatano, T. Shibayama, K. Munakata, Y. Sato, M. Uchida, K. Tsuchiya, S. Tanaka

    Journal of Nuclear Materials 367-370 B (SPEC. ISS.) 1382-1386 2007/08/01

    DOI: 10.1016/j.jnucmat.2007.04.001  

    ISSN: 0022-3115

  221. Influence of heat treatment on tritium distribution in V-4Cr-4Ti alloy Peer-reviewed

    H. Homma, Y. Hatano, H. Daifuku, H. Saitoh, T. Nagasaka, T. Muroga, M. Hara, Y. Nakamura, M. Matsuyama

    Journal of Nuclear Materials 367-370 A (SPEC. ISS.) 887-891 2007/08/01

    DOI: 10.1016/j.jnucmat.2007.03.051  

    ISSN: 0022-3115

  222. Diffusional behavior of tritium in V-4Cr-4Ti alloy Peer-reviewed

    K. Hashizume, J. Masuda, T. Otsuka, T. Tanabe, Y. Hatano, Y. Nakamura, T. Nagasaka, T. Muroga

    Journal of Nuclear Materials 367-370 A (SPEC. ISS.) 876-881 2007/08/01

    DOI: 10.1016/j.jnucmat.2007.03.239  

    ISSN: 0022-3115

  223. Probability of absorption/implantation of low-energy H<inf>2</inf>+ ions in O-covered vanadium Peer-reviewed

    A. Livshits, Y. Hatano, V. Alimov, M. Matsuyama

    Journal of Nuclear Materials 363-365 (1-3) 801-805 2007/06/15

    DOI: 10.1016/j.jnucmat.2007.01.103  

    ISSN: 0022-3115

  224. Diffusion and trapping of tritium in vanadium alloys Peer-reviewed

    J. Masuda, K. Hashizume, T. Otsuka, T. Tanabe, Y. Hatano, Y. Nakamura, T. Nagasaka, T. Muroga

    Journal of Nuclear Materials 363-365 (1-3) 1256-1260 2007/06/15

    DOI: 10.1016/j.jnucmat.2007.01.176  

    ISSN: 0022-3115

  225. Improvement in high temperature stability of Pd coating on Nb by Nb<inf>2</inf>C intermediate layer Peer-reviewed

    Yuji Hatano, Keita Ishiyama, Hirofumi Homma, Kuniaki Watanabe

    International Journal of Hydrogen Energy 32 (5) 615-619 2007/04

    DOI: 10.1016/j.ijhydene.2006.06.045  

    ISSN: 0360-3199

  226. Observation of Tritium Distribution in Low-Activation V-4Cr-4Ti Alloy by Radioluminography

    Sakamura Takashi, Saitoh Hideyuki, Homma Hirofumi, Hatano Yuji, Nagasaka Takuya, Muroga Takeo, Nakamura Yukio

    Journal of the Japan Institute of Metals and Materials 71 (5) 482-487 2007

    Publisher: The Japan Institute of Metals and Materials

    DOI: 10.2320/jinstmet.71.482  

    ISSN: 0021-4876

  227. Effects of bulk impurity concentration on the reactivity of metal surface: Sticking of hydrogen molecules and atoms to polycrystalline Nb containing oxygen Peer-reviewed

    Yuji Hatano, Kuniaki Watanabe, Alexander Livshits, Andrei Busnyuk, Vasily Alimov, Yukio Nakamura, Ken Ichi Hashizume

    Journal of Chemical Physics 127 (20) 2007

    DOI: 10.1063/1.2804874  

    ISSN: 0021-9606

  228. Development of PVD - TiAlN/a-C nanocomposite coating for pressure die casting applications Peer-reviewed

    Masateru Nose, Tokimasa Kawabata, Miki Ohi, Takekazu Nagae, Seiichi Masa, Yuji Hatano, Susumu Ikeno, Kiyoshi Nogi

    Plasma Processes and Polymers 4 (SUPPL.1) S681-S686 2007

    DOI: 10.1002/ppap.200731705  

    ISSN: 1612-8850

    eISSN: 1612-8869

  229. A newly developed non-destructive tritium measurement technique and its application to V-4Cr-4Ti alloy Peer-reviewed

    Xiang Liu, Xue Chen, H. Homma, Y. Hatano, M. Matsuyama

    Plasma Science and Technology 8 (6) 741-744 2006/11/01

    DOI: 10.1088/1009-0630/8/6/26  

    ISSN: 1009-0630

  230. Interactions between molten Flibe and metallic Be Peer-reviewed

    M. Hara, Y. Hatano, M. F. Simpson, G. R. Smolik, J. P. Sharp, Y. Oya, K. Okuno, M. Nishikawa, T. Terai, S. Tanaka, R. A. Anderl, D. A. Petti, D. K. Sze

    Fusion Engineering and Design 81 A (1-4) 561-566 2006/02

    DOI: 10.1016/j.fusengdes.2005.06.372  

    ISSN: 0920-3796

  231. Quantitative measurement of beryllium-controlled redox of hydrogen fluoride in molten Flibe Peer-reviewed

    Michael F. Simpson, Galen R. Smolik, John P. Sharpe, Robert A. Anderl, David A. Petti, Yuji Hatano, Masanori Hara, Yasuhisa Oya, Satoshi Fukada, Satoru Tanaka, Takayuki Terai, Dai Kai Sze

    Fusion Engineering and Design 81 A (1-4) 541-547 2006/02

    DOI: 10.1016/j.fusengdes.2005.08.031  

    ISSN: 0920-3796

  232. JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments Peer-reviewed

    David A. Petti, G. R. Smolik, Michael F. Simpson, John P. Sharpe, R. A. Anderl, S. Fukada, Y. Hatano, M. Hara, Y. Oya, T. Terai, D. K. Sze, S. Tanaka

    Fusion Engineering and Design 81 (8-14 PART B) 1439-1449 2006/02

    DOI: 10.1016/j.fusengdes.2005.08.101  

    ISSN: 0920-3796

  233. Influence of oxygen and carbon on performance of superpermeable membranes Peer-reviewed

    Y. Hatano, A. Livshits, Y. Nakamura, A. Busnyuk, V. Alimov, C. Hiromi, N. Ohyabu, K. Watanabe

    Fusion Engineering and Design 81 A (1-4) 771-776 2006/02

    DOI: 10.1016/j.fusengdes.2005.06.368  

    ISSN: 0920-3796

  234. Effects of bulk modification by Pd on electrochemical properties of MgNi Peer-reviewed

    Tiejun Ma, Yuji Hatano, Takayuki Abe, Kuniaki Watanabe

    Journal of Alloys and Compounds 391 (1-2) 313-317 2005/04

    DOI: 10.1016/j.jallcom.2004.08.071  

    ISSN: 0925-8388

  235. Hydrogen absorption capability of a niobium panel for pumping neutral atoms in divertor region Peer-reviewed

    Y. Nakamura, A. I. Livshits, Y. Nakahara, Y. Hatano, A. Busnyuk, N. Ohyabu

    Journal of Nuclear Materials 337-339 (1-3 SPEC. ISS.) 461-465 2005/03/01

    DOI: 10.1016/j.jnucmat.2004.10.012  

    ISSN: 0022-3115

  236. Influence of microstructure of tungsten on solid state reaction rate with amorphous carbon film Peer-reviewed

    Y. Hatano, M. Takamori, K. Nogita, K. Matsuda, S. Ikeno, K. Watanabe

    Journal of Nuclear Materials 337-339 (1-3 SPEC. ISS.) 902-906 2005/03/01

    DOI: 10.1016/j.jnucmat.2004.10.098  

    ISSN: 0022-3115

  237. Surface segregation of Ti in a V-4Cr-4Ti alloy and its influence on the surface reaction rates of hydrogen isotopes

    Y Hatano, R Hayakawa, K Nishino, S Ikeno, T Nagasaka, T Muroga, K Watanabe

    MATERIALS TRANSACTIONS 46 (3) 511-516 2005/03

    DOI: 10.2320/matertrans.46.511  

    ISSN: 1345-9678

    eISSN: 1347-5320

  238. Influence of heat treatment on hydrogen ingress into V-4Cr-4Ti alloy Peer-reviewed

    Ryo Hayakawa, Yuji Hatano, Ken Ichi Fukumoto, Hideki Matsui, Kuniaki Watanabe

    Journal of Nuclear Materials 329-333 (1-3 PART A) 411-415 2004/08/01

    DOI: 10.1016/j.jnucmat.2004.04.078  

    ISSN: 0022-3115

  239. Effects of Pd addition on electrochemical properties of MgNi

    Ma, T., Hatano, Y., Abe, T., Watanabe, K.

    Journal of Alloys and Compounds 372 (1-2) 2004

    DOI: 10.1016/j.jallcom.2003.09.148  

    ISSN: 0925-8388

  240. Kinetics of dissociative absorption of hydrogen through Nb surface covered by Oxygen Peer-reviewed

    Yuji Hatano, Alexander Livshits, Andrei Busnyuk, Mamoru Nomura, Kenici Hasizume, Masayasu Sugisaki, Yukio Nakamura, Nobuyoshi Ohyabu, Kuniaki Watanabe

    Physica Scripta T T108 14-18 2004

    DOI: 10.1238/Physica.Topical.108a00014  

    ISSN: 0281-1847

  241. Barrier effect against hydrogen ingress by Ti segregating to surface of V-Ti alloy Peer-reviewed

    Ryo Hayakawa, Yuji Hatano, Alexander Pisarev, Kuniaki Watanabe

    Physica Scripta T T108 38-41 2004

    DOI: 10.1238/Physica.Topical.108a00038  

    ISSN: 0281-1847

  242. Barrier effect against hydrogen ingress by Ti segregating to surface of V-Ti alloy

    Ryo Hayakawa, Yuji Hatano, Alexander Pisarev, Kuniaki Watanabe

    PHYSICA SCRIPTA T108 38-41 2004

    DOI: 10.1238/Physica.Topical.108a00038  

    ISSN: 0031-8949

  243. Kinetics of dissociative absorption of hydrogen through Nb surface covered by oxygen

    Yuji Hatano, Alexander Livshits, Andrei Busnyuk, Mamoru Nomura, Kenici Hashizume, Masayasu Sugisaki, Yukio Nakamura, Nobuyoshi Ohyabu, Kuniaki Watanabe

    PHYSICA SCRIPTA T108 14-18 2004

    DOI: 10.1238/Physica.Topical.108a00014  

    ISSN: 0031-8949

  244. Gas-driven hydrogen permeation in the surface-limited regime Peer-reviewed

    A. Pisarev, V. Shestakov, R. Hayakawa, Y. Hatano, K. Watanabe

    Journal of Nuclear Materials 320 (3) 214-222 2003/08/01

    DOI: 10.1016/S0022-3115(03)00110-7  

    ISSN: 0022-3115

  245. Hydrogen absorption by Pd-coated ZrNi prepared by using Barrel-Sputtering System Peer-reviewed

    M. Hara, Y. Hatano, T. Abe, K. Watanabe, T. Naitoh, S. Ikeno, Y. Honda

    Journal of Nuclear Materials 320 (3) 265-271 2003/08/01

    DOI: 10.1016/S0022-3115(03)00189-2  

    ISSN: 0022-3115

  246. Electrochemical studies of the effect of surface modification of amorphous MgNi electrodes by carbon or Ni Peer-reviewed

    Takayuki Abe, Sachio Inoue, Daobin Mu, Yuji Hatano, Kuniaki Watanabe

    Journal of Alloys and Compounds 349 (1-2) 279-283 2003/02/03

    DOI: 10.1016/S0925-8388(02)00901-5  

    ISSN: 0925-8388

  247. Flibe-D<inf>2</inf> permeation experiment and analysis

    Fukada, S., Anderl, R.A., Pawelko, R.J., Smolik, G.R., Schuetz, S.T., O{'}Brien, J.E., Nishimura, H., Hatano, Y., Terai, T., Petti, D.A., Sze, D.-K., Tanaka, S.

    Fusion Science and Technology 44 (2) 2003

    DOI: 10.13182/FST03-A369  

    ISSN: 1536-1055

  248. Surface segregation and oxidation of Ti in a V-Ti alloy Peer-reviewed

    Ryo Hayakawa, Yuji Hatano, Katsuhiko Fujii, Ken Ichi Fukumoto, Hideki Matsui, Kuniaki Watanabe

    Journal of Nuclear Materials 307-311 (1 SUPPL.) 580-584 2002/12

    DOI: 10.1016/S0022-3115(02)01100-5  

    ISSN: 0022-3115

  249. Solid state reaction between tungsten and amorphous carbon Peer-reviewed

    Yuji Hatano, Miyuki Takamori, Kenji Matsuda, Susumu Ikeno, Katsuhiko Fujii, Kuniaki Watanabe

    Journal of Nuclear Materials 307-311 (2 SUPPL.) 1339-1343 2002/12

    DOI: 10.1016/S0022-3115(02)00986-8  

    ISSN: 0022-3115

  250. Initial studies of tritium behavior in flibe and flibe-facing material Peer-reviewed

    S. Fukada, R. A. Anderl, Y. Hatano, S. T. Schuetz, R. J. Pawelko, D. A. Petti, G. R. Smolik, T. Terai, M. Nishikawa, S. Tanaka, A. Sagara

    Fusion Engineering and Design 61-62 783-788 2002/11

    DOI: 10.1016/S0920-3796(02)00204-1  

    ISSN: 0920-3796

  251. Surface modification of MgNi by perylene Peer-reviewed

    Tiejun Ma, Yuji Hatano, Takayuki Abe, Kuniaki Watanabe

    Materials Transactions 43 (11) 2711-2716 2002/11

    DOI: 10.2320/matertrans.43.2711  

    ISSN: 1345-9678

    eISSN: 1347-5320

  252. Fabrication of photocatalytic TiO<inf>2</inf> films on pure aluminum plates Peer-reviewed

    Susumu Ikeno, Tokimasa Kawabata, Hiroaki Hayashi, Kenji Matsuda, Seiichi Rengakuji, Toshiaki Suzuki, Yuji Hatano, Katsuyoshi Tanaka

    Materials Transactions 43 (5) 939-945 2002/05

    DOI: 10.2320/matertrans.43.939  

    ISSN: 1345-9678

    eISSN: 1347-5320

  253. Observation of hydrogen distribution in oxidized Zircaloy-2 with tritium microautoradiography Peer-reviewed

    Hitoshi Hanada, Yuji Hatano, Kanetsugu Isobe, Kan Sakamoto, Masayasu Sugisaki

    Fusion Science and Technology 41 (3 II) 915-918 2002/05

    DOI: 10.13182/fst02-a22718  

    ISSN: 1536-1055

  254. Superpermeability in fusion technology: Tritium accumulation and compression Peer-reviewed

    Alexander I. Livshits, Yuji Hatano, Kuniaki Watanabe

    Fusion Science and Technology 41 (3 II) 882-886 2002/05

    DOI: 10.13182/fst02-a22711  

    ISSN: 1536-1055

  255. Hydrogenation of MgNi2 by atomic hydrogen at elevated temperatures

    Y Hatano, K Watanabe

    MATERIALS TRANSACTIONS 43 (5) 1105-1109 2002/05

    DOI: 10.2320/matertrans.43.1105  

    ISSN: 1345-9678

    eISSN: 1347-5320

  256. Degradation kinetics of discharge capacity for amorphous Mg-Ni electrode Peer-reviewed

    D. Mu, Y. Hatano, T. Abe, K. Watanabe

    Journal of Alloys and Compounds 334 (1-2) 232-237 2002/02/28

    DOI: 10.1016/S0925-8388(01)01759-5  

    ISSN: 0925-8388

  257. Electrochemical behavior of amorphous MgNi as negative electrodes in rechargeable Ni-MH batteries Peer-reviewed

    Takayuki Abe, Tomoyuki Tachikawa, Yuji Hatano, Kuniaki Watanabe

    Journal of Alloys and Compounds 330-332 792-795 2002/01/17

    DOI: 10.1016/S0925-8388(01)01589-4  

    ISSN: 0925-8388

  258. Degradation of amorphous MgNi electrode and effect of heat treatment in Ar Peer-reviewed

    Yuji Hatano, Tomoyuki Tachikawa, Daobin Mu, Takayuki Abe, Kuniaki Watanabe, Shotaro Morozumi

    Journal of Alloys and Compounds 330-332 816-820 2002/01/17

    DOI: 10.1016/S0925-8388(01)01455-4  

    ISSN: 0925-8388

    eISSN: 1873-4669

  259. Relation between recombination rate constant of deuterium at niobium surface and oxygen concentration in bulk Peer-reviewed

    R. Hayakawa, A. Busnyuk, Y. Hatano, A. Livshits, K. Watanabe

    Physica Scripta T 103 113-116 2002

    ISSN: 0281-1847

  260. Diffusion behavior of sulfur in p(1×1) phase of S/Ni(1 0 0) system Peer-reviewed

    S. Tsukawaki, Y. Hatano, K. Hashizume, M. Sugisaki

    Surface Science 476 (1-2) 115-120 2001/03/20

    DOI: 10.1016/S0039-6028(00)01130-4  

    ISSN: 0039-6028

  261. Recovery of hydrogen isotopes by pd-coated zrni from inert gas atmosphere containing impurities

    Ashida, K., Hatano, Y., Nishida, W., Watanabe, K., Amano, A., Matsuda, K., Ikeno, S.

    Journal of Nuclear Science and Technology 38 (11) 2001

    DOI: 10.1080/18811248.2001.9715122  

    ISSN: 0022-3131

  262. Hydrogenation of MgNi2 by rf-discharged hydrogen plasma Peer-reviewed

    Y Hatano, K Watanabe

    PRICM 4: FORTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, VOLS I AND II 461-464 2001

  263. Diffusion behavior of sulfur in the p(1 × 1) phase of a S/Ni(111) system Peer-reviewed

    S. Tsukawaki, Y. Hatano, K. Hashizume, M. Sugisaki

    Surface Science 457 (1) 63-70 2000/06/01

    DOI: 10.1016/S0039-6028(00)00334-4  

    ISSN: 0039-6028

  264. Role of intermetallic precipitates in hydrogen transport through oxide films on Zircaloy Peer-reviewed

    Yuji Hatano, Masayasu Sugisaki, Koji Kitano, Masayuki Hayashi

    ASTM Special Technical Publication (1354) 901-917 2000

    DOI: 10.1520/stp14333s  

    ISSN: 1040-3094

  265. Permeation of hydrogen through vanadium under helium ion irradiation Peer-reviewed

    Yuji Hatano, Yoshiyasu Nanjo, Ryo Hayakawa, Kuniaki Watanabe

    Journal of Nuclear Materials 283-287 (PART II) 868-871 2000

    DOI: 10.1016/S0022-3115(00)00139-2  

    ISSN: 0022-3115

  266. Charge and discharge characteristics of sintered Mg<inf>2</inf>Ni Peer-reviewed

    Kuniaki Watanabe, Wei Min Shu, Kenzo Mizukami, Kohji Kobayashi, Yuji Hatano, Shotaro Morozumi

    Journal of Alloys and Compounds 293 626-631 1999/12/20

    Publisher: Elsevier Sequoia SA

    DOI: 10.1016/S0925-8388(99)00355-2  

    ISSN: 0925-8388

  267. Observation of spatial distribution of tritium in zirconium alloy with microautoradiography Peer-reviewed

    K. Isobe, Y. Hatano, M. Sugisaki, T. Hayashi, M. Nishi, K. Okuno

    Journal of Nuclear Materials 271-272 326-329 1999/05

    DOI: 10.1016/S0022-3115(98)00694-1  

    ISSN: 0022-3115

  268. Effect of surface modification by heating in argon on charge/discharge characteristics of Mg<inf>2</inf>Ni electrode Peer-reviewed

    Yuji Hatano, Tomoyuki Tachikawa, Koji Kobayashi, Katsunori Mori, Kuniaki Watanabe, Shotaro Morozumi

    Materials Transactions, JIM 40 (9) 919-922 1999

    Publisher: Japan Inst of Metals

    DOI: 10.2320/matertrans1989.40.919  

    ISSN: 0916-1821

  269. Hydrogen isotope electromigration and impurity effect in vanadium Peer-reviewed

    K. Fujii, K. Hashizume, Y. Hatano, M. Sugisaki

    Journal of Alloys and Compounds 282 (1-2) 38-43 1999

    DOI: 10.1016/S0925-8388(98)00827-5  

    ISSN: 0925-8388

  270. Transport mechanism of hydrogen through oxide film formed on zircaloy-4 Peer-reviewed

    Y. Hatano, R. Hitaka, M. Sugisaki, M. Hayashi

    Journal of Radioanalytical and Nuclear Chemistry 239 (3) 445-448 1999

    DOI: 10.1007/BF02349048  

    ISSN: 0236-5731

  271. Tracer diffusion coefficient of tritium in vanadium and trapping effect due to zirconium impurity

    K Fujii, K Hashizume, Y Hatano, M Sugisaki

    JOURNAL OF ALLOYS AND COMPOUNDS 270 (1-2) 42-46 1998/05

    DOI: 10.1016/S0925-8388(98)00354-5  

    ISSN: 0925-8388

  272. Influence of surface impurities on plasma-driven permeation of deuterium through nickel Peer-reviewed

    Yuji Hatano, Hirofumi Nakamura, Hirotaka Furuya, Masayasu Sugisaki

    Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films 16 (4) 2078-2083 1998

    DOI: 10.1116/1.581313  

    ISSN: 0734-2101

  273. Observation of the spatial distribution of hydrogen in Zircaloy-2 oxidized in H<inf>2</inf>O steam at 723 K by a technique of tritium microautoradiography Peer-reviewed

    K. Isobe, Y. Hatano, M. Sugisaki

    Journal of Nuclear Materials 248 315-318 1997/09/01

    DOI: 10.1016/S0022-3115(97)00129-3  

    ISSN: 0022-3115

    eISSN: 1873-4820

  274. Influence of size distribution of Zr(Fe,Cr)(2) precipitates on hydrogen transport through oxide film of Zircaloy-4

    Y Hatano, R Hitaka, M Sugisaki, M Hayashi

    JOURNAL OF NUCLEAR MATERIALS 248 (311-314) 311-314 1997/09

    DOI: 10.1016/S0022-3115(97)00128-1  

    ISSN: 0022-3115

  275. Auger electron spectroscopy study of oxidation behavior of iron and chromium in zr(fe, cr)<inf>2</inf> precipitate in zircaloy-4) Peer-reviewed

    Yuji Hatano, Masayasu Sugisaki

    Journal of Nuclear Science and Technology 34 (3) 264-268 1997/03

    DOI: 10.1080/18811248.1997.9733659  

    ISSN: 0022-3131

    eISSN: 1881-1248

  276. Oxidation behavior of iron and nickel in Zr<inf>2</inf>(Fe, Ni) precipitates in zircaloy-2

    Hatano, Y., Sugisaki, M.

    Journal of Nuclear Science and Technology 33 (11) 1996

    DOI: 10.1080/18811248.1996.9732016  

    ISSN: 0022-3131

  277. Measurement of diffusion coefficient of tritium in alpha-phase of zirconium based on glow discharge implantation method Peer-reviewed

    Ken ichi Hashizume, Yuji Hatano, Kan Sakamoto, Masayasu Sugisaki

    Fusion Technology 28 (3 pt 2) 1175-1178 1995/10

    DOI: 10.13182/fst95-a30567  

    ISSN: 0748-1896

  278. Characterization of surface barrier effect upon tritium permeation through stainless steel with auger electron spectroscopy Peer-reviewed

    Yuji Hatano, Toshio Maetani, Masayasu Sugisaki

    Fusion Technology 28 (3 pt 2) 1182-1187 1995/10

    DOI: 10.13182/fst95-a30569  

    ISSN: 0748-1896

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Misc. 97

  1. Tritium retention in gaps of first wall and divertor tiles used in JET-ITER like wall experiments

    波多野雄治, LEE Suneui, 増崎貴, 時谷政行, 大矢恭久, 宮本光貴, 芦川直子, 矢嶋美幸, 鳥養祐二, 大塚哲平, 朝倉伸幸, 中村博文, 林巧, WIDDOWSON Anna, RUBEL Marek, LIKONEN Jari

    日本原子力学会秋の大会予稿集(CD-ROM) 2023 2023

  2. Molecular dynamics simulation of double strand breaks in DNA telomere structure simulating tritium beta decay

    中村浩章, 中村浩章, 石黒健人, 藤原進, 中田彩子, 波多野雄治, 齋藤誠紀, 安永卓生, 米谷佳晃

    日本物理学会講演概要集(CD-ROM) 78 (1) 2023

    ISSN: 2189-079X

  3. Tritium Retention In JET-Divertor Tiles

    大和田篤志, 鳥養祐二, 矢嶋美幸, 菊地絃太, 増崎貴, 大塚哲平, 芦川直子, 芦川直子, 時谷政行, 大矢恭久, LEE S. E., 波多野雄治, 朝倉伸行, 林巧, 小柳津誠, LIKONEN J., WIDDOWSON A., RUBEL M.

    日本放射化学会討論会(Web) 66th 2022

  4. MD Evaluation on Tritium Decay of the Tolerance of DNA

    中村浩章, 中村浩章, 石黒健人, 宇佐見俊介, 斎藤誠紀, 藤原進, 波多野雄治

    プラズマ・核融合学会年会(Web) 39th 2022

  5. Mechanism of DNA Damage by Tritium-Fluorescence Microscope Observation of Double-Strand Breaks and Simulation

    藤原進, 波多野雄治, 中村浩章

    日本物理学会誌 77 (1) 2022

    ISSN: 0029-0181

  6. Molecular Dynamics Simulation on Tritium-Induced Damage of Biopolymers and Experimental System for Validation

    中村浩章, 中村浩章, 藤原進, 波多野雄治

    プラズマ・核融合学会誌 97 (10) 2021

    ISSN: 0918-7928

  7. 置換トリチウムのβ崩壊に伴う高分子・DNA構造変化の分子シミュレーション

    藤原進, 斉藤真司, 阿蘇司, 中村浩章, 安永卓生, 波多野雄治, 剣持貴弘, 斎藤誠紀, 大矢恭久, 坂井亙, 和田拓郎, 水口朋子, 米谷佳晃, 斎木敏治, 宮西寿典, 大塚教雄, 李浩論

    分子研レターズ 84 2021

    ISSN: 0385-0560

  8. Where Should We Handle Tritium? Information of Facilities and Laboratories

    96 (8) 420-422 2020/08

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  9. How to Start Tritium Experiments(1)Engineering and Scientific Applications of Tritium : Present and Future

    96 (6) 300-304 2020/06

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  10. FRONTIER Project (2019-2024)

    96 (3) 145-148 2020/03

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  11. Tritium Behavior and Its Neutron Irradiation Effect

    96 (3) 140-144 2020/03

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  12. Structural disruption of telomeric DNA by tritium beta decay

    中村浩章, 中村浩章, 宮西寿典, 藤原進, 水口朋子, 安永卓生, 中田彩子, 宮崎剛, 大塚教雄, 剣持貴弘, 波多野雄治, 斉藤真司, 尾又一実

    日本物理学会講演概要集(CD-ROM) 75 (1) 2020

    ISSN: 2189-079X

  13. Molecular dynamics simulation on structural change of polyethylene by beta decays of substituted-tritium

    藤原進, LI Haolun, 中村浩章, 中村浩章, 水口朋子, 安永卓生, 中田彩子, 宮崎剛, 大塚教雄, 剣持貴弘, 波多野雄治, 斉藤真司, 尾又一実

    日本物理学会講演概要集(CD-ROM) 75 (1) 2020

    ISSN: 2189-079X

  14. MD analysis on Structural Change of Deoxyribose in Telomeric DNA by Tritium Beta decay

    中村浩章, 中村浩章, 石黒健人, 藤原進, 水口朋子, 米谷佳晃, 安永卓生, 中田彩子, 宮崎剛, 大塚教雄, 剣持貴弘, 波多野雄治, 斉藤真司

    プラズマ・核融合学会年会(Web) 37th 2020

  15. Non-destructive depth profiling of tritium in graphite tiles from Large Helical Device using β-ray induced X-ray spectrometry and Monte Carlo simulation

    Lee Sun Eui

    38 (38) 1-8 2019/12/06

    Publisher: 富山大学研究推進機構水素同位体科学研究センター

    DOI: 10.15099/00020163  

    ISSN: 2433-5908

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    A special experimental setup was designed and constructed to perform simultaneousmultipoint measurements of β-ray induced X-ray spectra for non-destructive depthprofiling of tritium in plasma-facing tiles retrieved from fusion devices. The setupconsists of compact silicon drift detector and an airtight acrylic chamber. The plasmafacinggraphite tiles used in the deuterium experiment of Large Helical Device (LHD) inNational Institute for Fusion Science (NIFS) were examined. The obtained X-ray spectrawere simulated using Monte Carlo simulation tool kit Geant4. It has been found thattritium penetrated beyond the carbon deposition layer.

  16. DNAへのトリチウムのβ崩壊による構造変化

    中村浩章, 中村浩章, 宮西寿典, 藤原進, 水口朋子, 安永卓生, 中田彩子, 宮崎剛, 大塚教雄, 剣持貴弘, 波多野雄治, 斉藤真司

    プラズマ・核融合学会年会(Web) 36th 2019

  17. JET-ILW実験で使用されたWダイバータタイルおよびBeリミタタイルの微細構造

    時谷政行, 宮本光貴, 増崎貴, 波多野雄治, 大矢恭久, 大塚哲平, 濱口大, 黒滝宏紀, 小柳津誠, 鈴木卓美, 鈴木達也, 磯部兼嗣, 林巧, 朝倉伸幸, WIDDOWSON Anna, JACHMICH Stefan, RUBEL Marek

    プラズマ・核融合学会年会(Web) 36th 2019

  18. JET-ILW実験で生成されたダストの特性

    大塚哲平, 芦川直子, 芦川直子, 増崎貴, 波多野雄治, 鳥養祐二, 朝倉伸幸, 磯部兼嗣, 林巧, 時谷政行, 時谷政行, 大矢恭久, 谷川博康, 中道勝, WIDDOWSON Anna, RUBEL Marek

    プラズマ・核融合学会年会(Web) 36th 2019

  19. 炉内トリチウムインベントリの評価に向けて

    染谷洋二, 大矢恭久, 芦川直子, 波多野雄治, 増崎貴, 小林真, 大塚哲平, 信太祐二, 日渡良爾, 磯部兼嗣

    プラズマ・核融合学会年会(Web) 36th 2019

  20. タングステン二原子空孔の構造と水素による安定化に関する研究

    大沢一人, 山口正剛, 波多野雄治, 外山健, 渡邊英雄

    日本金属学会講演概要(CD-ROM) 164th 2019

    ISSN: 2433-3093

  21. Deuterium-trapping at irradiation-induced defects in tungsten studied by positron annihilation spectroscopy

    (12) 23-29 2019

    Publisher: 日本陽電子科学会

    ISSN: 2188-0107

  22. トリチウムからのβ線によるDNA二重鎖切断の定量的評価

    胡中優奈, 波多野雄治, 剣持貴弘, 大矢恭久, 中村浩章

    日本原子力学会春の年会予稿集(CD-ROM) 2018 2018

  23. トリチウムのヘリウム3への壊変によるポリエチレンの構造変化に関する分子動力学シミュレーション

    LI Haolun, 藤原進, 水口朋子, 橋本雅人, 中村浩章, 中村浩章, 安永卓生, 中田彩子, 宮崎剛, 大塚教雄, 剣持貴弘, 波多野雄治, 斉藤真司

    高分子学会予稿集(CD-ROM) 67 (2) 2018

  24. JET-ITER like wallから発生したダスト粒子のトリチウム保持特性

    大塚哲平, 増崎貴, 芦川直子, 波多野雄治, 朝倉伸幸, 鈴木卓美, 鈴木達也, 磯部兼嗣, 林巧, 時谷政行, 大矢恭久, 濱口大, 黒滝宏紀, 坂本隆一, 谷川博康, 中道勝, WIDDOWSON A., RUBEL M.

    日本原子力学会春の年会予稿集(CD-ROM) 2018 2018

  25. 高温中性子照射したタングステン中における水素同位体挙動

    大矢恭久, 小林真, 大塚哲平, 片山一成, 信太祐二, 山内有二, 原正憲, 波多野雄治, 島田雅, BUCHENAUER Dean, 加藤雄大

    核融合エネルギー連合講演会(CD-ROM) 12th 2018

  26. CuCrZr合金および酸化物分散強化Cu合金の水素同位体吸収・放出特性

    波多野雄治, SHI Peng, XIANG Xin, 外山健, 近藤創介, 檜木達也

    日本原子力学会春の年会予稿集(CD-ROM) 2018 2018

  27. 照射効果を考慮した核融合炉材料中の水素同位体蓄積量評価

    波多野雄治, ALIMOV Vladimir Kh., 大矢恭久, 近藤創介, 檜木達也, 染谷洋二

    核融合エネルギー連合講演会(CD-ROM) 12th 2018

  28. BCC金属中の空孔型欠陥の安定性と水素の影響

    大沢一人, 外山健, 山口正剛, 波多野雄治, 渡邊英雄

    日本金属学会講演概要(CD-ROM) 162nd 2018

    ISSN: 2433-3093

  29. タングステン二原子空孔中の水素の安定構造とその同位体の影響

    大沢一人, 波多野雄治, 山口正剛, 外山健, 渡邊英雄

    日本金属学会講演概要(CD-ROM) 163rd 2018

    ISSN: 2433-3093

  30. MD simulation on DNA decay by Tritium disintegration to Helium-3

    Nakamura Hiroaki, Hatano Yuji, Saito Shinji, Miyanishi Hisanori, Fujiwara Susumu, Mizuguchi Tomoko, Yasunaga Takuo, Nakata Ayako, Miyazaki Tsuyoshi, Otsuka Takao, Kenmotsu Takahiro

    Meeting Abstracts of the Physical Society of Japan 73 (0) 368-368 2018

    Publisher: The Physical Society of Japan

    DOI: 10.11316/jpsgaiyo.73.2.0_368  

  31. Tritium Behavior and Neutron Irradiation Effect

    93 (3) 139-143 2017/03

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  32. Neutron Irradiation Plan

    93 (3) 133-135 2017/03

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  33. 中性子による炭素材料の特性変化と核融合炉への適応性評価

    渥美寿雄, 波多野雄治, 庭瀬敬右, 車田亮, 大塚哲平

    東北大学金属材料研究所附属量子エネルギー材料科学国際研究センター共同利用研究経過報告書(CD-ROM) 34 2017

  34. 欠陥導入タングステン中の水素同位体滞留量に及ぼす炭素・ヘリウム照射影響

    東奎介, 戸苅陽大, ZHOU Qilai, 波多野雄治, 吉田直亮, 近藤創介, 檜木達也, 島田雅, TAYLOR Chase N., BUCHENAUER Dean A., KOLASINSKI Robert D., 近田拓未, 大矢恭久

    日本原子力学会秋の大会予稿集(CD-ROM) 2017 2017

  35. 金属中の二原子空孔の安定構造と水素の影響

    大沢一人, 山口正剛, 外山健, 波多野雄治, 渡邊英雄

    日本金属学会講演概要(CD-ROM) 161st 2017

    ISSN: 2433-3093

  36. Development of triton target for measurement of a two neutron transfer reaction in inverse kinematics.

    Koiwai Takuma, Kumon Taku, Shimizu Yuma, Niikura Mugumi, Imai Nobuaki, Hatano Yuji, Wimmer Kathrin

    Meeting Abstracts of the Physical Society of Japan 72 (0) 357-357 2017

    Publisher: The Physical Society of Japan

    DOI: 10.11316/jpsgaiyo.72.1.0_357  

  37. Superabundant vacancy formation induced by hydrogen in tungsten

    Osawa Kazuhito

    (148) 25-33 2015/03

    Publisher: Research Institute for Applied Mechanics, Kyushu University

    DOI: 10.15017/1543589  

    ISSN: 1345-5664

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    We investigate superabundant vacancy formation induced by hydrogen (H) in tungsten (W) in terms of an equilibrium thermodynamic model. Stable configulations of multiple H atoms trapped in a W vacancy and binging enegies are estimated by first-principle calculations. The structures of H atoms in a W vacancy are abnormal compared with those in usual bcc transition metals, that is, a maximum of 12 H atoms can be accommodated in the vacancy. Isotope effects are examined by taking into account zero point vibration energies of the H atoms. The profiles of vacancy-hydrogen (V-H) cluster concentrations in a bulk tungsten are calculated as a function of the H concentration at finite temperature. V-H clusters trapping more than six H atoms exist in the present model. However, the major V-H clusters are composed of six H atoms in a wide range of temperature and H concentration.

  38. ダスト粒子中のトリチウム定量技術の開発

    大塚哲平, 波多野雄治

    日本原子力学会春の年会予稿集(CD-ROM) 2015 2015

  39. Direct measurement of retained tritium in dust particles released from JET-ILW

    芦川直子, 芦川直子, 朝倉伸幸, 磯部兼嗣, 小柳津誠, 原正憲, WIDDOWSON A., GRZONKA J., RUBEL M., 大塚哲平, 黒滝宏紀, 濱口大, 中野優, KIM J.H., 波多野雄治, 谷川博康, 中道勝, 山西敏彦

    プラズマ・核融合学会年会(Web) 32nd 2015

  40. Surface Properties and Retention of Helium in Stainless Steel Exposed to LHD Plasmas

    35 1-12 2015

    Publisher: 富山大学研究推進機構水素同位体科学研究センター

    DOI: 10.15099/00016649  

    ISSN: 2433-5908

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    Modification of the plasma facing surface of LHD and its effects on the retention and desorption of He were examined by exposing 316L stainless steel coupons to LHD plasmas. In the erosion dominant area, formation of dense He bubbles and mixing of deposited impurities (C, O, Fe, Cr, Ni) occurred in a subsurface region of about 20 nm-thick. In the deposition dominant area, the surface was covered by a porous carbon rich layer. Retention of He was saturated in both areas. In the erosion dominant area, He was trapped by the radiation-induced defects formed in the very thin subsurface region. The concentration of He trapped in the impurity deposition (He/C) in the deposition dominant area was estimated to be 0.9%.

  41. Plasma-Wall Interaction Studies using Linear Plasma Devices

    HATANO Yuji, MIYAMOTO Mitsutaka, SHIMADA Masashi, UEDA Yoshio, TOKITANI Masayuki

    90 (8) 489-495 2014/08

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  42. Retention Enhancement of Hydrogen Isotope in Tungsten Exposed to LHD Plasma

    OYA Yasuhisa, MASUZAKI Suguru, TOKITANI Masayuki, WATANABE Hideo, YOSHIDA Naoaki, HATANO Yuji, MIYAMOTO Mitsutaka, YAMAUCHI Yuji, HINO Tomoaki, OKUNO Kenji

    90 (6) 319-324 2014/06

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  43. 種々の照射欠陥を導入したタングステン中の水素同位体滞留挙動

    大矢恭久, 佐藤美咲, 湯山健太, ZHANG Long, 近藤創介, 檜木達也, 波多野雄治, 吉田直亮, 奥野健二

    核融合エネルギー連合講演会(CD-ROM) 10th 2014

  44. Measurements of Carbon Deposition Layers using Glow-Discharge Optical Emission Spectroscopy (GDOES)

    34 21-30 2014

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006567  

    ISSN: 1346-3675

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    In fusion devices with plasma-facing components manufactured from carbon-based materials, co-deposition of hydrogen isotopes and carbon takes place in regions where sputtering rate is relatively small. Fuel retention and recycling depend on properties of those deposits. Glow-discharge optical emission spectroscopy (GDOES) is one of attractive techniques to analyze chemical composition and thickness of these deposition layers. However, influence of hydrogen content on sputtering of these layers by glow-discharge plasma is not fully understood. In this study, two different types of carbon layer with quite different hydrogen content were deposited on stainless steel substrate, and sputtering rate during the GDOES measurement was examined for better interpretation of results obtained.

  45. Irradiation-Tritium Synergism

    HATANO Yuji, OYA Yasuhisa, HARA Masanori, ODA Takuji, OTSUKA Teppei, SATO Koichi, ZHANG Kun

    89 (11) 725-730 2013/11

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  46. A New Japan-US Joint Research Project : PHENIX

    UEDA Yoshio, HATANO Yuji

    89 (11) 749-751 2013/11

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  47. Magnetic properties of ZrNi-H systems

    33 9-19 2013

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006556  

    ISSN: 1346-3675

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    We estimate the amount of hydrogen isotope gas stored in getter materials without using a desorption process and by measuring the magnetic susceptibility of ZrNi-H systems. The magnetic susceptibility of ZrNiH x increased with an increase in the hydrogen content, x, reaching a maximum value at x ? 0.5. As x > 0.5, the magnetic susceptibility began to decrease and reached a minimum value at x= 2.7. The behavior of magnetic susceptibility could be qualitatively modeled using the molar fractions of the ZrNi, monohydride, and trihydride phases observed using X-ray diffraction analysis.

  48. Development of a double-walled cell system for near-infrared spectroscopy

    33 35-43 2013

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006559  

    ISSN: 1346-3675

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    Near-infrared spectroscopy has potential as a new suitable tool to detect tritiated water (HTO, T2O). We previously carried out the initial study with a single-walled cell system and got some spectra of tritiated water vapor. Because of the radioactive nature of tritium, tritiated water was decomposed into tritium gas and oxygen by radiochemical reactions, and there was a need for a reoxidizing system and other updates to improve tritium recycling and safety issues. Therefore, we developed a new double-walled cell system and tested its basic performance. The performance of the cell was found to be appropriate for the prolonged measurement of the spectra of tritiated water vapor.

  49. Tritium Systems of Fusion Reactor

    YAMANISHI Toshihiko, HATANO Yuji, AKAMARU Satoshi, ASAKURA Yamato, ISOBE Kanetsugu, IWAI Yasunori, OKUNO Kenji, ODA Takuji, OYA Yasuhisa, SUGIYAMA Takahiko, TANAKA Satoru, TORIKAI Yuji, NAKAMURA Hirofumi, HAYASHI Takumi, HARA Masanori

    88 (9) 508-528 2012/09/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  50. Thermodynamic properties of vacancy-hydrogen complex in tungsten

    Ohsawa Kazuhito, Hatano Yuuji, Yamaguchi Masatake, Hatano Yuji

    Reports of Research Institute for Applied Mechanics,Kyushu University (143) 29-32 2012/09

    Publisher: Research Institute for Applied Mechanics, Kyushu University

    DOI: 10.15017/27132  

    ISSN: 1345-5664

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    Formation energies for vacancy-hydrogen (V-H) complexes in tungsten (W) are calculated in terms of first-principles calculations. The dependence of concentration of V-H complexes on temperature and local H concentration is estimated assuming thermal equilibrium. It has been reported that a maximum of 12 H atoms are accommodated in a W monovacancy at 0 K. However, major monovacancies trap six H atoms in finite temperature.

  51. Sticking of H_2 on Oxygen-Covered Surface of Vanadium Doped with Oxygen to Various Bulk Concentrations

    Livshits Alexander, Busnuk Andrei, Alimov Vasily

    31 (31) 33-48 2012/03/30

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006534  

    ISSN: 1346-3675

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    The sticking probability of Hz on the surface of polycrystalline V covered with oxygen was examined as a function of oxygen concentration in the bulk metal (0.4 to 3.3 at.%) at specimen temperatures from 200 to 1000℃. At all temperatures examined, the sticking probability was strongly dependent on the oxygen concentration in the bulk.Such correlation between the reaction rate of Hz on the surface and the oxygen concentration in the bulk was attributed to the dependence of concentration of oxygen vacancies (holes in surface oxygen coverage) on the oxygen bulk concentration. The values of sticking probability were relatively high even at the oxygen bulk concentration of 3.3 at.%; the oxygen coverage on vanadium was rather "holey" even at the oxygen concentration close to the solubility limit. The activation energy for H_2 dissociation on such holes in the coverage was evaluated to be 10 kJ/mol H_2.

  52. 大型プラズマ装置に設置したタングステン試料中の水素同位体滞留能変化

    大矢恭久, 小林真, 藤島徹生, 増崎貴, 時谷政行, 吉田直亮, 日野友明, 山内有二, 波多野雄治, 奥野健二

    日本原子力学会春の年会予稿集(CD−ROM) 2012 (0) ROMBUNNO.A15-702 2012/03/02

    Publisher: 一般社団法人 日本原子力学会

    DOI: 10.11561/aesj.2012s.0.702.0  

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    近年、核融合炉第一壁にはタングステンの利用が検討されている。タングステン中の水素滞留量はグラファイトと比較すると少ないが、照射損傷の有無によって大きく変化することがこれまでに多く報告されている。しかし、実際の核融合炉では種々の高エネルギー粒子による照射損傷のみならず、不純物等の堆積によってタングステン材料の水素滞留能力は大きく変化することが考えられる。そこで、本研究では大型プラズマ装置におけるプラズマ曝露によってタングステンの水素滞留能力がどのように変化する評価した。

  53. Deuterium Retention in Self-Damaged Tungsten with and without Deposited Pd Layer

    Alimov VladimirKh

    32 9-20 2012

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006544  

    ISSN: 1346-3675

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    Influence of Pd deposition on deuterium (D) retention in W samples irradiated with W self-ions was examined to understand the correlation between the probability of occupation of radiation-induced traps by D and the concentration of D in a solid solution state under plasma exposure. W samples were irradiated with 4.8 MeV W ions to 0.65 and 12 dpa, and a thin Pd layer was deposited on the sample with the higher damage level by a technique of sputter-deposition. Then, the samples were exposed to DC glow-discharge D plasma at 403 K. In spite of the higher damage level, the concentration of trapped D in the damaged zone of the Pd-covered sample was far smaller than that in the non-covered one. The small D retention in the Pd-covered sample was explained by a decrease in the D concentration in the solution state owing to the enhanced recombinative release by Pd and the consequent reduction in the occupation probability of radiation-induced traps. These observations indicated that tritium inventory in neutron-irradiated W materials can be significantly reduced by enhancement of tritium reemission by surface modifications.

  54. Accomplishments of the Large Amount of Tritium Handling Technology (1) : Accumulation of the Safety Operation Experiences of Tritium Handling Facilities and the Related Safety Studies

    HATANO Yuji, YAMADA Masayuki, HAYASHI Takumi

    Journal of plasma and fusion research 86 (3) 173-184 2010/03/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  55. トリチウムプラズマ照射した金属材料表面および内部のトリチウム挙動(TITAN)

    大塚哲平, 島田雅, 上田良夫, 波多野雄治, CALDERONI P., SHARPE J.P., 田辺哲朗

    核融合エネルギー連合講演会(CD-ROM) 8th 2010

  56. Tritium Permeation, Contamination and Decontamination

    HATANO Yuji, TORIKAI Yuji, OYA Yasuhisa, ODA Takuji, TANAKA Satoru, NAKAMURA Hirofumi, ASAKURA Yamato, OHUCHI Hiroko, OTSUKA Teppei, KOBAYASHI Kazuhiro

    Journal of plasma and fusion research 85 (10) 726-735 2009/10/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  57. Study on Molten-Salt Flibe Systems : 2. 1 Chemical Behavior of Flibe Molten Salt

    TERAI Takayuki, FUKADA Satoshi, HATANO Yuji, OYA Yasuhisa

    Journal of plasma and fusion research 85 (5) 251-257 2009/05/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  58. The Way to Know Tritium Transfer Process in Gaseous and Liquid Phases

    FUKADA Satoshi, HATANO Yuji, HARA Masanori

    Journal of plasma and fusion research 85 (1) 31-35 2009/01/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  59. Visualization of Hydrogen Distribution in Nuclear Materials with Tritium

    HATANO Yuji, SAITOH Hideyuki, HOMMA Hirofumi

    Materia Japan 47 (12) 617-617 2008/12/01

    Publisher: The Japan Institute of Metals and Materials

    DOI: 10.2320/materia.47.617  

    ISSN: 1340-2625

  60. Tritium distribution on/beneath mechanically-treated surface of vanadium

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 28 33-42 2008

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006512  

    ISSN: 1346-3675

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    Tritium distribution on/beneath a mechanically-treated surface of vanadium was examined by an imaging plate (IP) technique. Enrichment of tritium was observed around WC indentation lefts and was ascribed to the trapping effects of defects induced by plastic deformation. 0n the other hand, such an increase in tritium concentration was not observed around the lefts of Vickers indentation due to a smaller extent of plastic deformation and higher compressive stress. The accuracy and spatial resolution of the IP technique were sufficient to distinguish the difference in tritium distributions in the areas treated by two different methods.

  61. Thremal Diffusion of Tritium in Vanadium alloys

    Ogushi Kazuhiro, Masuda Josuke, Hashizume Kenichi, Otsuka Teppei, Tanabe Tetsuo, Hatano Yuji, Nakamura Yukio, Nagasaka Takuya, Muroga Takeo

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2007 (0) 852-852 2007

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2007f.0.852.0  

  62. Correlation between Hydrogen Distribution in V-4Cr-4Ti Alloy and Impact Strength

    Hatano Yuji, Homma Hirofumi, Sakamura Takashi, Saitoh Hideyuki, Nagasaka Takuya, Muroga Takeo, Matsuyama Masao

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2007 (0) 851-851 2007

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2007f.0.851.0  

  63. Absorption and release of hydrogen isotopes by ZrC

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 27 27-36 2007

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006505  

    ISSN: 1346-3675

  64. バナジウム合金中のトリチウム挙動

    橋爪健一, 益田丈輔, 大塚哲平, 田辺哲朗, 波多野雄治, 中村幸男, 長坂琢也, 室賀健夫

    核融合エネルギー連合講演会予稿集 6th 2006

  65. Diffusion of hydrogen in TiC

    HATANO Y.

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 26 31-43 2006

    Publisher: 富山大学水素同位体科学研究センター

    DOI: 10.15099/00006498  

    ISSN: 1346-3675

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    The diffusion coefficient of hydrogen in commercially supplied TiC powder was measured at 773, 873 and 973 K by hydrogen absorption experiments. The pre-exponential factor and activation energy were evaluated to be 10-11 m2? s-1 and 87±13 kJ?mol-1, respectively.

  66. 視点--還る 水素同位体を利用した循環型エネルギーシステム

    波多野 雄治, 阿部 孝之

    未来材料 5 (8) 2-5 2005/08

    Publisher: エヌ・ティー・エス

    ISSN: 1346-0986

  67. Nuclear Materials and Hydrogen (3) ; Hydrogen Energy Materials

    HATANO Yuji, INOUE Mitsuhiro, ABE Takayuki, NAKAMORI Yuko, ORIMO Shinichi, NAGASAKI Takanori

    Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 47 (1) 15-24 2005/01/30

    Publisher: Atomic Energy Society of Japan

    DOI: 10.3327/jaesj.47.15  

    ISSN: 0004-7120

  68. In-situ measurements of tritium desorption from a vanadium alloy by β-ray-induced X-ray spectrometry (BIXS)

    Liu Xiang, Homma H., Hatano Y., Matsuyama M.

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 25 63-70 2005

    Publisher: Toyama University

    DOI: 10.15099/00006492  

    ISSN: 1346-3675

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    Thermal release of tritium from a vanadium alloy was investigated by means of β-ray-induced X-ray spectrometry (BIXS). The sample tested was a V-4Cr-4Ti alloy recrystallized by annealing at 1000 ?C for 2 h. A tritium gas diluted with hydrogen was characterized with a quadrupole mass spectrometer and a small ionization chamber, and the concentration of tritium was evaluated to be 0.14%. The sample was exposed to the tritium gas at 400 ?C. The total concentration of hydrogen isotopes absorbed in the sample was 0.17 at%, and the corresponding tritium concentration was 2.4 appm, respectively. Tritium started to desorb at 350 ?C. The duration of time required for desorption was much longer than that expected from the diffusion coefficient of tritium in the alloy, indicating that the rate of tritium release was controlled by a surface recombination process.

  69. Adsorption and Segregation of Hydrogen on Clean Nb Surface

    Hatano Y., Alimov V., Livshits A., Nakamura Y., Ohyabu N., Matsuyama M

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 25 25-39 2005

    Publisher: Toyama University

    DOI: 10.15099/00006489  

    ISSN: 1346-3675

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    Sticking coefficient of H2, α , on a clean Nb surface was measured as a function of specimen temperature (25 - 477 ?C) and hydrogen uptake. The initial value of sticking coefficient at negligible hydrogen uptake was ca. 0.25 and was independent of surface temperature. At any temperature examined, α showed a significant reduction with increase in hydrogen uptake, although the extent of reduction decreased with increasing temperature. Such reduction in α was ascribed to the increase in the surface coverage of hydrogen due to surface segregation and was explained by a model assuming equilibrium partitioning of hydrogen between the surface and the solid solution phase in the bulk.

  70. Dissociative Absorption of Hydrogen through Nb Surface Covered by Oxygen

    Hatano Yuji, Livshits Alexander, Busnyuk Andrei, Alimov Vassili, Hashizume kenichi, Nakamura Yukio, Ohyabu Nobuyoshi, Watanabe Kuniaki

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2004 (0) 702-702 2004

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2004s.0.702.0  

  71. Influence of Oxygen and Sulfur on Hydrogen Absorption by Vanadium

    Hayakawa Ryo, Nishino Kanako, Hatano Yuji, Alimov Vasily, Livshits Alexander, Ikeno Susumu, Nakamura Yukio, Ohyabu Nobuyoshi, Watanabe Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University 24 9-28 2004

    Publisher: Toyama University

    DOI: 10.15099/00006483  

    ISSN: 1346-3675

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    Sticking coefficient of H2, α, on a vanadium surface was measured after heat treatments in vacuum at 673, 873, 973 and 1273 K. The values of α were comparable after heat treatments at 673, 873 and 973 K, while significant reduction was observed after heat treatment at 1273 K. Arrhenius plots of α showed that the pre-exponential factor, α0, was far smaller than unity for all heat treatment conditions. This observation indicated that only minor portions of surface sites were active for hydrogen ingress. Change in chemical surface state of V by heat treatments in vacuum at 673, 873, 1073 and 1273 K was also investigated by means of X-ray photoelectron spectroscopy. The specimen surface was mainly covered by VO at 673 K and by an oxygen adlayer at 873 K. Sulfur appeared at 1073 K and completely substituted for oxygen at 1273 K. Namely, sulfur became the dominant surface impurity in the temperature region where α showed significant reduction. It was therefore concluded that the barrier effect of oxygen, including formation of a VO layer, was much weaker than that of sulfur under the present conditions.

  72. Construction of Computer System for Dose Assessment and its Operation

    HARA Masanori, AKAMARU Satoshi, HATANO Yuji, MATSUYAMA Masao, SHIBAO Yukinobu, WATANABE Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University 24 47-53 2004

    Publisher: Toyama University

    DOI: 10.15099/00006486  

    ISSN: 1346-3675

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    A computer system for dose assessment was installed to evaluate radiation dose of each worker in a controlled area and to automatically produce reports on dose assessment. The main computer was connected to both a tritium monitor control computer and a gate control computer. This computer network has been isolated from a public network. The gate control computer registers data on working hours of each worker in the controlled area and on tritium concentration of each room. The dose assessment computer acquires essential data from the gate control computer to evaluate the radiation dose of each worker. The potential of the specialized network system to improve dose assessment was examined over a period of two years. It was found that this system significantly contributed to improvement of dose assessment. The basis of assessment was made clear, and reports on dose assessment without errors were readily produced.

  73. Novel techniques of Pd coating for hydrogen storage materials and permeation membranes (共著)

    Proceedings of 15th World Hydrogen Energy Conference 2004

  74. HYDROGEN ABSORPTION BY VANADIUM ALLOYS

    Hatano Yuji, Hayakawa Ryo, Watanabe Kuniaki

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2003 (0) 572-572 2003

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2003f.0.572.0  

  75. Study of Hydrogen Adsorption by V, V-Ti alloy and V-oxide through ab initio Calculations

    WANG L., Hayakawa R., Hatano Y., Watanabe K.

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 23 29-41 2003

    Publisher: Toyama University

    DOI: 10.15099/00006479  

    ISSN: 1346-3675

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    The adsorption of hydrogen on surfaces of vanadium, vanadium-titatnium alloy and vanadium oxide was studied by ab initio calculations using Gaussian03 package. The activation and adsorption energies for adsorption were evaluated by scanning potential energy surfaces of respective systems comprising a hydrogen molecule and small cluster consisting of several metal atoms for modelling an alloy surface to reduce computational cost. The surfaces investigated were V(110), V-Ti(110), VO(111) and VO(110), diaerent cluster models being adopted for some surfaces to examine their validities and to and an appropriate cluster model and adsorption site. By comparing the results obtained by using the alloy and/or compound in diaerent cases, it was found that the activation energy for adsorption is larger for surfaces with an oxygen adlayer than for clean and Ti-covered vanadium surfaces. These andings are in good agreement with experimental observations. It was also demonstrated that diaerent cluster models for a given alloy give similar activation and adsorption energies.

  76. Addition of Some Transition Elements and their Effects on the Electrochemical Properties of MgNi

    Ma Tiejun, Hatano Yuji, Abe Takayuki, Watanabe Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 23 43-52 2003

    Publisher: Toyama University

    DOI: 10.15099/00006480  

    ISSN: 1346-3675

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    In this study, some transition elements, Ag, Co, Pd, Re, Ru and Ti, at 6 and 10mol% compositions, were selected to ball mill with Mg2Ni and Ni, and the effects of transition elements on the electrochemical properties of amorphous MgNi were investigated. Three distinct effects on the electrochemical properties of MgNi were found: Ti and Pd dissolved into the bulk of MgNi during ball milling and the degradation of discharge capacity was decreased by addition of Ti and Pd. Ag and Co also dissolved in the MgNi powder, but there was no appreciable influence on the electrochemical behavior of MgNi. Re and Ru neither dissolved into MgNi nor improved the properties of MgNi.

  77. Sputtering of Oxygen on Nb Surface by Hydrogen Ions

    Hatano Yuji, Busnyuk Andrei, Livshits Alexander, Nakamura Yukio, Ohyabu Nobuyoshi, Watanabe Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 23 17-27 2003

    Publisher: Toyama University

    DOI: 10.15099/00006478  

    ISSN: 1346-3675

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    The rate of oxygen removal from an oxygen-doped Nb membrane by hydrogen ion sputtering was examined by measuring the change in the sticking coefficient of H2, α. First, the temperature dependence of α was measured at various oxygen concentrations to investigate correlation between bulk oxygen concentration and α. Then the oxygen concentration in the membrane was adjusted to 1.5 at%, and the surface of the membrane was irradiated by hydrogen ions of 600 eV at 1113 K. The change in α with sputtering time was measured, and the reduction in bulk oxygen concentration was estimated from the extent of change in α. The oxygen concentration decreased with increasing sputtering time by continuous surface segregation of oxygen and sputtering. The sputtering yield of oxygen on the Nb membrane surface was evaluated to range from 0.012 to 0.036.

  78. 金属膜中の水素の超透過とその応用への可能性

    波多野 雄治

    まてりあ : 日本金属学会会報 41 (9) 652-652 2002/09/20

    ISSN: 1340-2625

  79. Effects of Pd Addition on the Electrochemical Properties of MgNi

    Ma Tiejun, Hatano Yuji, Abe Takayuki, Watanabe Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 22 35-46 2002

    Publisher: Toyama University

    DOI: 10.15099/00006472  

    ISSN: 1346-3675

  80. Correlation between microstructure of tungsten and solid state reaction rate with amorphous carbon film

    Takamori Miyuki, Hatano Yuji, Watanabe Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 22 47-53 2002

    Publisher: Toyama University

    DOI: 10.15099/00006473  

    ISSN: 1346-3675

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    The correlation between microstructure of tungsten and rate of carbide formation was investigated at 800 ℃ by examining the reaction between amorphous carbon films and tungsten specimens fabricated under different conditions. The carbide formed was W2C, and no WC was observed. The growth rate of W2C showed no significant dependence on the size and shape of crystal grains. A clear correlation, however, was observed between the hardness of tungsten and the rate of W2C growth, and the reaction rate decreased with hardness.

  81. Construction and Performance Test of Apparatus for Permeation Experiments with Controlled Surfaces

    Hatano Yuji, Nomura Mamoru, Watanabe Kuniaki, Livshits Alexander I., Busnyuk Andrei O., Nakamura Yukio, Ohyabu Nobuyoshi

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 21 13-26 2001

    Publisher: Toyama University

    DOI: 10.15099/00006462  

    ISSN: 1346-3675

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    A new apparatus was constructed to examine gas-, atom- and Plasma-driven permeation of hydrogen isotopes through group VA metal membranes with precisely controlled surface states. Absorption and desorption experiments are also possible. The new apparatus consists of two vacuum chambers, an upstream chamber and a downstream chamber, separated by a specimen membrane. Both chambers are evacuated by turbo-molecular pumps and sputter-ion pumps. The upstream chamber is equipped with Ta filaments serving as atomizers in atom-driven permeation experiments and cathodes in plasma-driven permeation experiments. The specimen membrane is formed into a tubular and electrically isolated from the chamber. Hence, ohmic heating of the membrane is possible, and this feature of the membrane is suitable for surface cleaning by high-temperature heating and impurity doping for the control of surface chemical composition through surface segregation. Both chambers were evacuated to 1x10-7 Pa after baking. The main component of residual gas was H2, and the partial pressures of impurity gases other than H2 were ca. 1x10-8 Pa. Gas- and atom-driven permeation experiments were successfully carried out with hydrogen gas for Nb membrane activated by heating in vacuum at 1173K. Superpermeation was observed in the atom-driven permeation experiments. Absorption experiments with a clean surface were also carried out. The surface was, however, cleaned only partially, because the temperature distribution was not uniform during high-temperature heating. Nevertheless, surface cleanliness was retained during absorption experiments under the present vacuum conditions. A new membrane assembly that will enable a uniform temperature distribution is now under construction.

  82. Solid State Reaction between Tungsten and Amorphous Carbon Film

    Hatano Yuji, Watanabe Kuniaki, Takamori Miyuki, Matsuda Kenji, Ikeno Susumu

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 20 31-41 2000

    Publisher: Toyama University

    DOI: 10.15099/00006457  

    ISSN: 1346-3675

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    Solid state reaction between tungsten and carbon film was examined at 1073K. Carbon film was deposited onto tungsten sheet by vacuum evaporation at room temperature and analyzed by means of X-ray photoelectron spectroscopy. Carbon and tungsten beneath the carbon film were detected, whereas only trace amount of impurities such as oxygen were present. The binding energy of W 4f electrons indicated that tungsten was in a metallic state at the interface. These observations suggested that no impurity layer existed at the interface. Analysis using transmission electron microscopy showed that carbon was in an amorphous state. The specimen was heated at 1073 K in vacuum, and change in crystal structure was analyzed by means of X-ray diffraction. The peak of W2C appeared after an induction period for ca. 1 min, although W2C is not thermodynamically stable at 1073 K. The peak intensity ratio of W2C to metallic tungsten increased in proportion to the square root of time to take the maximum value at 50 min and then decreased with elapse of time. No peak of WC was observed. These results indicate that the nucleation rate of W2C was much faster than that of WC at 1073 K. The decomposition of W2C was ascribed to the reaction between carbon in W2C and H2O in residual gas.

  83. Kinetic Analysis of Reactions between Hydrogen-containing Carbon Film and Substrate Metals(Be,Mo,W)

    Ashida Kan, Hatano Yuji, Watanabe Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 20 43-52 2000

    Publisher: Toyama University

    DOI: 10.15099/00006458  

    ISSN: 1346-3675

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    Kinetic analyses were performed for solid-state reactions between a hydrogen-containing carbon film and substrate metals to form metallic carbide of Me2C (Me=Be, Mo, W). Isothermal and non-isothermal reaction curves could be explained by a random nucleation and two-dimentional crystal growth model. The kinetic equation can be approximated well by -ln(1-x)= kappt2, where x is the extent of reaction and kapp the apparent rate constant. The temperature dependence of the rate constants are given as kapp(Be)=3.10 exp(-109.[kJ/mol]/RT) [1/sec2], kapp(Mo)=231. exp(-161.[kJ/mol]/RT), kapp(W) =516. exp(-183.[kJ/mol]/RT), for Be-C, Mo-C and W-C systems, respectively, where the apparent activation energy is considered to be the sum of those for nucleation and diffusion. Linear relations were found between the apparent activation energy and the melting point of substrate metals as well as the bond strength of Me-C (Me=Be, Mo, W).

  84. Measurement of Diffusion Coefficient of Sulfur Adsorbed on Ni(111) Surface.

    TSUKAWAKI Satoshi, HATANO Yuji, HASHIZUME Kenichi, SUGISAKI Masayasu

    Hyomen Kagaku 21 (2) 102-106 2000

    Publisher: The Surface Science Society of Japan

    DOI: 10.1380/jsssj.21.102  

    ISSN: 0388-5321

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    The diffusion coefficient of sulfur in the p(1&times;1) phase of a S/Ni(111) system has been measured in a temperature region from 486 K to 577 K by micro-probe Auger electron spectroscopy, in which the initial coverage profile of sulfur is prepared by depositing sulfur molecules in a localized circular area. The diffusion coefficient measured is in agreement with that reported in our previous paper, in which H2S gas was used as a sulfur source and the initial coverage profile of sulfur was prepared by argon ion sputtering. It has been concluded that surface roughness of nickel, supposedly brought about by argon ion sputtering used in our previous work, does not exert appreciable influence upon the diffusion behavior of sulfur.

  85. Redistribution of Hydrogen in Fuel Cladding and Its Influence on Mechanical Properties of Cladding under Dry Storage Conditions

    Hashizume Kenichi, Hatano Yuji, Seki Rumi, Sugisaki Masayasu

    Engineering sciences reports, Kyushu University(Kyushu Daigaku Sogorikogaku Kenkyuka hokoku) 21 (3) 281-288 1999/12

    Publisher: Kyushu University

    DOI: 10.15017/16566  

    ISSN: 0388-1717

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    Hydrogen redistribution process in Zircaloy cladding of spent fuels was evaluated under the thermal condition of dry storage. Charpy impact test was carried out at temperatures from room temperature to 523 K on two kinds of Zircaloy specimens including 400 wt-ppm of hydrogen:One is the specimen in which hydrogen (hydride)is uniformly distributed and the other in which hydrogen is nonuniformly distributed. These tests show that the impact strength of the specimen with non-uniform hydrogen distribution is larger than that of the specimen with uniform distribution. On the basis of these results, the possibility that the impact strength of the cladding including large amount of hydrogen is degraded during the dry storage was suggested;e.g. in the case of the cladding including 400 ppm hydrogen, the uniform distribution of hydrogen is realized when the cladding is heated up to 773 K.

  86. Performance Test of Tritium Experimental System for 100Ci/run(2) : Hydrogen Isotope Separation Unit

    HARA Masanori, MATSUYAMA Masao, ASHIDA Kan, HATANO Yuji, KAGO Munekazu, WATANABE Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 19 1-7 1999

    Publisher: Toyama University

    DOI: 10.15099/00006447  

    ISSN: 1346-3675

  87. Charge/Discharge Characteristics of Amorphous MgNi Electrode and Influence of Heat Treatment in Argon

    Hatano Yuji, Tachikawa Tomoyuki, Mu Daobin, Abe Takayuki, Watanabe Kuniaki, Morozumi Shotaro

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 19 21-31 1999

    Publisher: Toyama University

    DOI: 10.15099/00006449  

    ISSN: 1346-3675

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    An amorphous MgNi alloy was prepared by mechanical alloying, and its charge/discharge characteristics were examined in a 6 M KOH solution at room temperature. The discharge capacity of the alloy was large than that of conventional AB5 alloys in the initial stage of charge/discharge cycles, but it decreased promptly with an increase in cycle number. The cell voltage in the charge process increased with the cycles. Degradation in the discharge capacity also occurred owing to immersion in the KOH solution under an open circuit potential. Since the formation of a Mg(OH)2 layer was observed by X-ray diffraction analysis, the degradation of the electrode was ascribed to the increase in overvoltage in the charge process by the Mg(OH)2 layer formed on the alloy surface through the chemical reaction between the alloy and the KOH solution. The effect of heat treatment on the charge/discharge characteristics was also examined. The discharge capacity of amorphous MgNi and MgNi0.6Co0.4 alloys decreased in the initial stage of the cycle test by heating in argon owing to recrystallization. The degradation rates of these alloys, however, were also reduced by heating at 300℃, and the heated alloys showed large discharge capacity compared with unheated ones after 10 cycles. These results were attributed to the increase in surface area of the alloys brought about by selective evaporation of magnesium.

  88. Influence of Surface Oxide Film on Hydrogen Permeation through Vanadium Membrane

    HAYAKAWA Ryo, HATANO Yuji, WATANABE Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 19 57-64 1999

    Publisher: Toyama University

    DOI: 10.15099/00006452  

    ISSN: 1346-3675

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    Temperature dependence of hydrogen permeation rate was examined for a vanadium membrane oxidized at room temperature by exposure to air. Pressure dependence of the permeation rate was also examined to determine the rate-controlling process of the permeation. The change in the chemical state of surface oxide by heating in vacuum was analyzed by X-ray photoelectron spectroscopy (XPS). The permeation rate was small below 300℃ and significantly increased in the temperature range from 300 to 400℃. The rate-controlling process of the permeation was determined as surface reaction because the permeation rate increased in proportion to the upstream pressure. A surface oxide film consisting of V2O3 and VO was formed on the vanadium surface. At almost the same temperature at which the permeation rate increased, V2O3 and VO were reduced to metal. Hence, the increase in permeation rate at a temperature above 300℃ was ascribed to the reduction of V2O3 and VO to metal. The reduction of V2O3 to metal took place via VO.

  89. Performance Test of Tritium Experimental System for 100Ci/run (1) : Detritiation Device for Exhaust Gases

    HARA Masanori, MATSUYAMA Masao, ASHIDA Kan, HATANO Yuji, SHU W. M., WATANABE Kuniaki

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 18 (18) 33-41 1998

    Publisher: Toyama University

    DOI: 10.15099/00006440  

    ISSN: 0916-8486

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    A tritium experimental system for 100Ci/run was established at the Hydrogen Isotope Research Center, Toyama University. This system consisted of two distinct experimental chambers for tritium experiments and backup components such as tritium storage-supply, gas purification, isotope separation and exhaust-gas detritiation. To confirm the reliability of the detritiation device, which is an important factor of the system, the basic performance of the detritiation device was assessed using a small amount of tritium. Two different methods were examined: one is based on conventional oxidation-adsorption (wet method) and the other gettering (dry method). The wet method is advantageous if exhaust gases include large amounts of impurities such as oxygen, water, hydrocarbon and so on. The dry method is applicable for processing exhaust gases which mainly include elemental tritium with a small amount of impurities. The wet method showed excellent performance for tritium removal from exhaust gases with impurity oxygen, the initial tritium concentration was reduced below 1/10 within 20 min. Similar performance was also obtained by dry method. In addition, the absorption bed loaded with molecular sieves could be regenerated by applying the dry method. Accordingly, it was concluded that the performance of the detritiation device satisfies requirement for performing tritium experiments.

  90. Influence of Pre-oxidation on Charge/Discharge Characteristics of Sintered Mg2Ni

    HATANO Y., KOBAYASHI Koji, MORI Katsunori, WATANABE Kuniaki, MOROZUMI Shotaro

    Annual report of Hydrogen Isotope Research Center,Toyama University,Japan 18 (18) 105-116 1998

    Publisher: Toyama University

    DOI: 10.15099/00006446  

    ISSN: 0916-8486

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    The influence of pre-oxidation on charge/discharge characteristics of sintered Mg2Ni electrodes was examined with an open electrochemical cell. Mg2Ni powder was first oxidized slightly in air at 473 K for 5-360 min and then sintered in argon atmosphere at 823 K. The cyclic stability of discharge capacity was improved markedly by pre-oxidation. Maximum cycle life was obtained using 20 min pre-oxidation. The mechanism by which pre-oxidation influences cyclic stability was examined via density measurement and surface analysis. The sintering rate had a maximum value for 20 min pre-oxidation. An MgO layer was formed on the surface of Mg2Ni during sintering and growth rate of the MgO layer decreased with pre-oxidation. Improvement of cyclic stability with pre-oxidation was attributed to the firm aggregation between Mg2Ni powder particles due to reduction in the thickness of MgO layer.

  91. Role of Intermetallic Precipitates in Hydrogen Uptake of Zircaloy-2

    HATANO Yuji, ISOBE Kanetsugu, HITAKA Ryuji, SUGISAKI Masayasu

    Journal of Nuclear Science and Technology 33 (12) p.944-949 1996/12/25

    Publisher: Atomic Energy Society of Japan

    DOI: 10.3327/jnst.33.944  

    ISSN: 0022-3131

    More details Close

    The hydrogen uptake behavior of two types of Zircaloy-2 specimens containing either fine intermetallic precipitates or coarse ones was studied at 623-723K in the pre-transition period of oxidation to clarify the role of the precipitates in the hydrogen transport through the oxide film. In the former case, the amount of hydrogen taken up was small and did not show the oxidation temperature dependence. In the latter case, the amount of hydrogen taken up was large and dependent markedly upon the oxidation temperature; it increased with decreasing oxidation temperature. These results were successfully explained with the model that the intermetallic precipitates remaining in a metallic state in the oxide film act as the fast transport route of hydrogen.

  92. 原子力に携わる者として

    波多野 雄治

    日本原子力学会誌 = Journal of the Atomic Energy Society of Japan 37 (3) 211-211 1995/03/30

    ISSN: 0004-7120

  93. Observation of Hydrogen Distribution in Zircaloy-2 by Tritium Microautoradiography

    16 (4) 369-373 1995/03/01

    Publisher: 九州大学大学院総合理工学研究科

    DOI: 10.15017/17352  

    ISSN: 0388-1717

    More details Close

    Zircaloy-2 specimens were oxidized in steam and charged with tritium by the cathodic charging method. The distribution of tritium in the oxide film and alloy was observed by microautoradiography. Although tritium was absorbed by the alloy through the oxide film, the tritium concentration in the oxide film and alloy layer beneath it was lower than the concentration in the inner region of alloy. In the oxide film and alloy layer beneath it, tritum segregated in intermetallic precipitates. In the inner region of alloy, tritium segregated in the intermetallic precipitates and the grain boundary of zirconium matrix.

  94. Influence of Oxide Film on Dissolution Rate of Gaseous Tritium into SUS-316 Stainless Steel

    14 (1) 9-15 1992/06/01

    Publisher: 九州大学大学院総合理工学研究科

    DOI: 10.15017/17258  

    ISSN: 0388-1717

    More details Close

    Characterization of surface impurities on SUS-316 stainless steel was performed with an Auger electron spectroscopy, the surface of which was prepared in two ways. Oxygen impurity was not observed on the surface annealed at 1273K in vacuum but segregation of appreciable amount of sulfur was observed. A duplex oxide layer of chromium and iron oxides was observed on the surface exposed to air at room temperature after vacuum annealing. Summarizing these experimental results and the data of our previous experiment on measurement of dissolution rate of gaseous tritium into the present stainless steel, the barrier effect of oxide film on the dissolution rate of gaseous tritium into stainless steel was discussed. The disappearance of barrier effect of the present duplex oxide film under a reducing conditions was ascribed to the reconstruction of oxide film resulted from the reduction of top layer of iron oxide.

  95. Modification of Surface Impurities on Nickel Membrane Exposed to RF-Discharged Hydrogen Plasma and Its Influence on the Plasma-Driven Permeation

    Hatano yuji, Kumano Hideki, Sugisaki Masayasu

    13 (2) 163-169 1991/09/01

    Publisher: 九州大学大学院総合理工学研究科

    DOI: 10.15017/17226  

    ISSN: 0388-1717

    More details Close

    Modification of surface impurities on nickel membrane exposed to rf-discharged hydrogen plasma at room temperature and 500℃ was examined with Auger electron spectroscopy. The main impurities were oxygen, carbon, and sulfur. Their concentration was reduced with exposure to the hydrogen plasma. At room temperature, sulfur was completely removed but carbon formed nickel carbide. At 500℃, sulfur and carbon were completely removed. At every temperature, oxygen was not completely removed on the contrary oxygen and silicon were deposited on the surface in case of exposure for long time, which was ascribed to the sputtering of pyrex glass. These results were related to our previous experiment of the plasma-driven permeation of hydrogen through nickel and the influence of the surface impurities on the transient behavior of the plasma-driven permeation was discussed.

  96. Measurement of Dissociation Rate of RF-Discharged Deuterium Plasma and Rate-Determining Processes of Plasma-Driven Permeation Through Nickel Membrane

    12 (2) 169-174 1990/09/01

    Publisher: 九州大学大学院総合理工学研究科

    DOI: 10.15017/17190  

    ISSN: 0388-1717

    More details Close

    The transient permeation flux of deuterium through nickel membrane was measured in a temperature region from 373K to 773K by use of the RF-discharged deuterium plasma. The experimental results were analysed by the diffusion-controlled model and it was concluded that the permeation rate of the plasma driven permeation under the present experimental conditions was controlled by the diffusion process at temperatures below 480K and by the surface recombination process at temperatures above 480K. The significantly enhanced permeation flux observed in our study was ascribed to the fact that neutral deuterium atoms impinging onto the specimen surface have a larger dissolution rate than that of the deuterium molecules by the order of 107.

  97. Construction of Apparatus for Plasma-Driven Permeation Experiment and Permeation Behavior of Deuterium Plasma Through Ni Membrane

    11 (3) 279-285 1989/12/01

    Publisher: 九州大学大学院総合理工学研究科

    DOI: 10.15017/17155  

    ISSN: 0388-1717

    More details Close

    An apparatus for plasma-driven permeation experiment has been constructed, in which the plasma is produced by the RF-dischange. The permeation behavior of deuterium plasma through Ni membrane has been examined and the significantly enhanced permeation flux has been confirmed. Following mechanisms have been proposed for the plasma-driven permeation of deuteriuln through Ni. (i) Neutral deuterium atoms make a predominant contribution to the permeation enhancement. (ii) Electrons also take part in the permeation enhancement by inducing the dissociation of deuterium molecules adsorbed on the Ni surface. The experimental conditions under which the permeation spike occurs have been examined and an origin of the permeation spike has ascribed to the enhancement of recombination on the up-stream surface which is brought about by the dischargecleaning of the Ni surface during the permeation experiment.

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Books and Other Publications 3

  1. アクティブラーニングで学ぶ震災・復興学

    六花出版 2020

  2. Tritium : fuel of fusion reactors

    Tanabe, Tetsuo

    Springer 2017

    ISBN: 9784431564584

  3. 核融合炉燃料(共著)(市村憲司編 水素の物性・反応の機能性化と応用)

    アイピーシー 2001

Presentations 53

  1. Global Distribution of Tritium in JET with the ITER-Like Wall Invited

    Y.Hatano, S. E. Lee, S. Masuzaki, Y. Oya, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, K. Isobe, H. Kurotaki, D. Hamaguchi, T. Hayashi, J. Likoneng, S. Koivuranta, A. Widdowson, S. Jachmich, M. Rubel, JET contributors

    The 24th International Conference on Plasma Surface Interaction in Fusion Devices 2021/01/24

  2. Isotope Effects on Hydrogen Retention, Trapping and Permeation in Copper-Based Materials

    Yuji Hatano, Xiang Xin, Peng Shi, Takeshi Toyama, Naoki Ebisawa, Sosuke Kondo, Tatsuya Hinoki

    The 19th International Conference on Fusion Reactor Materials 2019/10/29

  3. Overview of Japan-US Project PHENIX: Technological Assessment of He-Cooled Divertor with Tungsten for DEMO Reactors Invited

    Yuji Hatano, Daniel Clark, Yoshio Ueda, Yutai Katoh, Takehiko Yokomine, Minami Yoda, Adrian S. Sabau, Tatsuya Hinoki, Akira Hasegawa, Lauren M. Garrison, J. Wilna Geringer, Yasuhisa Oya, Masashi Shimada, Dean Buchenauer, Takeo Muroga

    The 14th International Symposium on Fusion Nuclear Technology 2019/09/24

  4. Hydrogen Isotope Retention and Transport in Neutron-Irradiated Tungsten Invited

    Yuji Hatano

    TRANSAT Tritium School 2019/03/26

  5. Fuel retention and transport in tungsten: neutron irradiation, seeded impurities, alloying and isotope effects Invited

    Y. Hatano, V. Kh. Alimov, K. Schmid, R. Doerner, Y. Ueda

    The 22nd International Conference on Plasma Surface Interactions in Controlled Fusion Devices 2016/05/30

  6. Deuterium Trapping at Defects Created with Neutron- and Ion-Irradiation in Tungsten

    Y. Hatano1, M. Shimada, Y. Oya, V. Kh. Alimov, M. Hara, J. Shi, M. Kobayashi, T. Oda, G. Cao, K. Okuno, T. Tanaka, K. Sugiyama, J. Roth, B. Tyburska-Püschel, J. Dorner, N. Yoshida, N. Futagami, H. Watanabe, M. Sokolov, Y. Katoh

    The 24th IAEA Fusion Energy Conference

  7. Trapping of hydrogen isotopes by radiation defects formed in W by neutron and ion irradiations

    Y. Hatano, M. Shimada, V.Kh. Alimov, J. Shi, M. Hara, Y. Oya, M. Kobayashi, K. Okuno, T. Oda, G. Cao, N. Yoshida, N. Futagami, K. Sugiyama, J. Roth, B. Tyburska-Püschel, J. Dorner, I. Takagi, M. Hatakeyama, H. Kurishita, M. Sokolov

    The 20th International Conference on Plasma Surface Interactions in Controlled Fusion Devices

  8. Tritium detection: challenges and photonic approaches

    Yuji Hatano

    The13th International Confernece on Photonics and Applications 2024/10/16

  9. タングステン及びタングステン・レニウム合金の高温酸化機構に関する研究

    小林 真, 大塚 哲平, 大矢 恭久, 能登 裕之, 島田 雅, 波多野 雄治

    日本原子力学会 2024年秋の大会

  10. 中性子照射タングステン材料の高温酸化挙動および放射化酸化物放出挙動

    松本 あずさ, 波多野 雄治, 大塚 哲平, 小林 真, 大矢 恭久, 島田 雅

    日本原子力学会 2024年秋の大会

  11. Effects of irradiation temperature on microstructure and hardness in W-0.3Cr alloy after irradiation with 6.4 MeV Fe ions

    Jing Wang, Yifan Zhang, Takeshi Toyama, Kiyohiro Yabuuchi, Yuji Hatano

    15th China-Japan Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering

  12. Influence of molybdenum addition on He bubble formation in tungsten

    Kotaro Fukuda, Yuji Hatano, Yajima Miyuki, Naoaki Yoshida, Daisuke Nagata

    15th China Japan Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering

  13. Effects of hydrogen isotopes on stability of vacancy-type defects in tungsten

    Eijiro Taguchi, Yuji Hatano, Toshiharu Takahashi, Takeshi Toyama

    15th China Japan Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering

  14. Tritium permeation and oxidation behavior of Inconel 600 under high temperature, high pressure water environment

    Azusa Matsumoto, Yuji Hatano

    15th China Japan Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering

  15. Interactions between Hydrogen Isotope and Vacancy-type Defects in Metals

    Yuji Hatano

    15th China Japan Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering 2024/09/05

  16. 電子線照射されたタングステン中の原子空孔形成に対するレニウム添加効果

    外山 健, Zhang Zhaokuan, 井上耕治, 永井康介, 木野村淳, 波多野雄治

    第61回 アイソトープ・放射線研究発表会

  17. タングステン中のHeバブル形成に及ぼすモリブデン添加の影

    福田耕太郎, 波多野雄治, 矢嶋美幸, 吉田直亮, 永田大介

    第15回核融合エネルギー連合講演会

  18. タングステン中の空孔型⽋陥の安定性に及ぼす⽔素同位体の影響

    田口瑛爾朗, 波多野雄治, 外山健, 高橋俊晴

    第15回核融合エネルギー連合講演会

  19. ヘリウム照射したタングステン合⾦中のバブル形成挙動に与える添加元素の影響

    森俊也, Joshua Ashley, 波多野雄治, 大矢泰久, 宮本光貴

    第15回核融合エネルギー連合講演会

  20. タングステンからのHeの放出速度に及ぼすモリブデンの影響

    福田 耕太郎, 波多野 雄治

    日本原子力学会 2024年春の年会

  21. ODS FeCrAl合金が形成するα-Al2O3被膜の密着強度と液体金属浸漬の影響に関する研究

    北村 嘉規, 近藤 正聡, 畑山 奨, 大野 直子, 菱沼 良光, 坂本 寛, 波多野 雄治, Pint Bruce, Jun Jheon, Romedenne Marie

    日本原子力学会 2024年春の年会

  22. トリチウムトレーサー法を用いた金属材料中の非金属介在物による水素捕捉の研究

    波多野 雄治, 西村 瑞規

    日本原子力学会 2024年春の年会

  23. 放射線規制及び災害に対応可能な実践力を有する放射線取扱主任者育成の取組み

    大矢 恭久, 波多野 雄治, 原 正憲, 横山 明彦, 山田 記大, 立松 憲次郎, 片山 一成, 納冨 昭弘, 城間 吉貴, 濱田 栄作

    日本原子力学会 2024年春の年会

  24. 高温高圧水/水蒸気雰囲気下におけるインコネル600の酸化挙動およびトリチウム透過への影響

    松本あずさ, 波多野雄治

    日本原子力学会 2024年春の年会

  25. トリチウムを利用した鉄鋼中の水素捕捉に関する研究

    西村瑞規, 波多野雄治

    令和5年度日本鉄鋼協会北陸信越支部・日本金属学会北陸信越支部連合講演会 2023/12/02

  26. ステンレス鋼への炭素ドーピングによる⽔素透過の抑制

    信太 祐二, 波多野雄治, 佐々木浩一

    プラズマ・核融合学会 第40回年会

  27. ⾦属から⾼温⾼圧⽔中へ流⼊したトリチウムのインコネル600を介した透過

    松本あずさ, 波多野雄治

    プラズマ・核融合学会 第40回年会

  28. JET ILWで使⽤されたタングステンバルクダイバータタイルポロイダルギャップに蓄積された共堆積層の特性解析

    時谷政行, 宮本光貴, 増崎貴, 波多野雄治, Sun Eui Lee, 大矢恭久, 黒滝宏紀, 朝倉伸幸, 中村博文, 林 巧, Marek Rubel, Anna Widdowson, Jari Likonen

    プラズマ・核融合学会 第40回年会

  29. WおよびW-Reにおける重水滞留に及ぼすHe照射効果

    加用敦也, 星野柚香, 三福寺旭, 周啓来, 波多野雄治, 大矢恭久

    プラズマ・核融合学会 第40回年会

  30. イオンビーム解析装置を⽤いたQUESTプラズマ対向壁材料の⽔素同位体吸蔵評価

    矢嶋美幸, 吉田直亮, 花田和明, 増崎貴, 大宅諒, 波多野雄治, 時谷正行

    プラズマ・核融合学会 第40回年会

  31. 材料中の損傷と燃料粒子の相互作用とダイナミクス

    波多野雄治

    プラズマ・核融合学会 第40回年会

  32. Co-deposited layers on the poloidal gap surface of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures

    Masayuki Tokitani, Mitsutaka Miyamoto, Suguru Masuzaki, Yuji Hatano, Sun Eui Lee, Yasuhisa Oya, Hironori Kurotaki, Nobuyuki Asakura, Hirofumi Nakamura, Takumi Hayashi, Marek Rubel, Anna Widdowson, Jari Likonen, JET Contributors

    21th International Conference on Fusion Reactor Materials

  33. Evaluation of Hydrogen Embrittlement and SCC Resistance of ODS-Cu, Cu-Cr-Zr, and Cu-Cr Alloys by SSRT Method

    Masahiko Hatakeyama, Yuto Asai, Mizuki Nisimura, Yuji Hatano, Daichi Nakato, Satoshi Sunada, Koichi Sato

    21th International Conference on Fusion Reactor Materials

  34. In-situ He bubble formation in W and W-Mo alloys

    Joshua Ashley, Mitsutaka Miyamoto, Yuji Hatano, Kiyohiro Yabuuchi, Takeshi Toyama, Masayuki Tokitani, Enrique Jimenez-Melero

    21th International Conference on Fusion Reactor Materials

  35. Irradiation Responses of Selected Binary Tungsten Alloys

    Yuji Hatano

    21th International Conference on Fusion Reactor Materials

  36. Overview of Japan-US Collaboration FRONTEIR Project —Fusion Research Oriented to Neutron Irradiation Effects and Tritium Behavior at Material Interfaces—

    Yuji Hatano

    15th International Symposium on Fusion Nuclear Technology

  37. Tritium permeation through Inconel 600 under high temperature, high pressure water environment: Influence of oxidation of coexisting materials

    Azusa Matsumoto, Yuji Hatano

    15th International Symposium on Fusion Nuclear Technology

  38. LHD重水素実験における第一壁・ダイバータ板へのトリチウム蓄積研究

    増崎 貴, 矢嶋 美幸, 田中 将裕, 本島 厳, 森崎 友宏, 時谷 政行, 大塚 哲平, 吉田 直亮, 大矢 恭久, 波多野 雄治

    日本原子力学会 2023年秋の大会

  39. JET-ITER like wall実験で使用された第一壁およびダイバータタイルのギャップへのトリチウム蓄積

    波多野 雄治, Lee Suneui, 増崎 貴, 時谷 政行, 大矢 恭久, 芦川 直子, 中村 博文, 林 巧, Widdowson Anna, Rubel Marek

    日本原子力学会 2023年秋の大会

  40. 一次系内に共存する金属材料の酸化が高温高圧水環境下でのインコネル600中のトリチウム透過に及ぼす影響

    松本 あずさ, 波多野 雄治

    一次系内に共存する金属材料の酸化が高温高圧水環境下でのインコネル600中のトリチウム透過に及ぼす影響

  41. Enhanced vacancy annihilation in irradiated W by addition of Re and Cr − What is the mechanism? − Invited

    Y. Hatano, J. Wang, T. Toyama

    International Workshop on Models and Data for Plasma-Material Interaction in Fusion Devices 2023/05/30

  42. Tritium Research Activities in Hydrogen Isotope Research Center, University of Toyama Invited

    Y. Hatano, M. Hara, M. Matsuyama

    Symposium about Tritium Science and Technology 2023/05/25

  43. タングステン中の水素同位体の蓄積・拡散における照射効果とその抑制 Invited

    波多野雄治

    日本金属学会シンポジウム―タングステン材料科学- 2022/12/08

  44. Impact of irradiation on fuel retention in fusion reactor materials

    Yuji Hatano

    13th International Conference Tritium Science and Technology

  45. Tritium in chamber materials, trapping and release (plasma chamber in DEMO, irradiation damage and tritium trapping) Invited

    Yuji Hatano

    IAEA Technical Meeting on Plasma Physics and Technology Aspects of the Tritium Fuel Cycle for Fusion Energy

  46. 水素同位体の基礎 物性と応用 Invited

    波多野雄治

    軽金属学会第142回春期大会

  47. Fuel retention in and removal from neutron irradiated tungsten Invited

    Y. Hatano, M. Yajima, V. Kh. Alimov, T. Toyama, Y. Nobuta, Y. Oya, T. Kuwabara, K. Suzuki, T. Schwarz Selinger, A. V. Spitsyn, A. Matsumoto, N. Ohno

    18th International Conference on Plasma-Facing Materials and Components for Fusion Applications

  48. Retention and Transport of Tritium and Hydrogen Isotopes in Fusion Reactor Materials

    Yuji Hatano

    2019/04/25

  49. Hydrogen Isotope Retention and Permeation in Cu Alloys and Isotope Effects

    Yuji Hatano, Peng Shi, Xiang Xin

    The 12th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering 2018/09/26

  50. Research Progress on Hydrogen Isotope Behaviors in Neutron-Irradiated Tungsten Invited

    Yuji Hatano, Yasuhisa Oya, Takeshi Toyama, Miyuki Yajima, Tatsuya Kuwabara, Noriyasu Ohno

    Plasma Conference 2017 2017/11/22

  51. Effects of W Deposition on Surface Modification and Sputtering Erosion of Fe under Exposure to Deuterium Plasma

    The 13th China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering 2016/09/26

  52. Overview of Recent Japanese Activities on Measurement of Tritium in Solid Materials

    Yuji Hatano, Kazuya Yumizuru, Hiroko Yoshida-Ouchi, Teppei Otsuka, Makoto Oyaidzu, Kanetsugu Isobe, Takumi Hayashi

    The 1st Asia-Pacific Symposium on Tritium Science 2015/11/03

  53. Wet-Chemical Method for Fabrication of Tritium Permeation Barrier Coatings Invited

    Yuji Hatano, Kun Zhang

    The 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications 2011/05/12

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Industrial Property Rights 1

  1. 金属表面への被膜生成方法

    波多野 雄治, 張 鯤, 孔 祥か

    特許第5569896号

    Property Type: Patent

    Holder: 富山大学

Research Projects 45

  1. HT recovery from tritiated water by laser irradiation

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Challenging Research (Pioneering)

    Institution: University of Toyama

    2023/06/30 - 2026/03/31

  2. Dynamic interactions of lattice defects and hydrogen isotopes in tungsten and its influence on tritium behavior

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: University of Toyama

    2022/04/01 - 2026/03/31

  3. 三重水素標的と大強度三重水素ビームによる中性子多体系の探究

    三木 謙二郎, 上坂 友洋, 波多野 雄治, 今井 伸明

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 基盤研究(B)

    Category: 基盤研究(B)

    Institution: 東北大学

    2020/04/01 - 2024/03/31

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    本研究では、三重水素標的を製作し、それと大強度三重水素ビームを組み合わせて原子核反応測定を行うことで、原子核系が高アイソスピン状態にある場合についての基礎データを取得することを目指している。 本年度は特に三重水素標的の製作について重点的に実施した。三重水素標的としては、チタン吸蔵型を採用した。過去の我々の研究により、薄膜に効率よく水素ガスを吸蔵させていく方法は確立していた。しかし、ガス中に微量の不純物が存在しているだけでも吸蔵の障害となるという問題がみられた。そこで、多少不純物が存在する環境下でも水素ガスを吸いやすい製作条件を事前に探索した。その上で、標的の実製作を富山大学の水素同位体科学研究センターにおいて実施した。その結果、厚さ約80ミクロンのチタンフォイルに、チタン原子に対して三重水素原子を1.5倍まで吸蔵させた標的を製作することに成功した。これは原子核物理用のチタン吸蔵型三重水素標的としては世界最高の厚さである。製作した標的は、今後の加速器実験に利用する為に、専用の多重密封チェンバーに封じた上で、理化学研究所へと輸送した。 また標的製作と並行して、加速器実験で使用する為の実験装置の開発も推進した。標的を設置する為の真空チェンバーの開発を行うとともに、散乱粒子の散乱角度を決定する為の短冊形シンチレーション検出器のテスト機の製作を実施した。後者については、必要性能を満たすことを確認するところまでが完了し、実機の製作へと話を進めることができた。

  4. Plasma driven permeation for plasma facing materials and its hydrogen isotope effect

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Shizuoka University

    2020/04/01 - 2023/03/31

  5. 高温・水素雰囲気照射法の開発によるフェライト鋼の中性子照射劣化への水素効果の解明

    外山 健, 秋山 英二, 波多野 雄治

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 基盤研究(B)

    Category: 基盤研究(B)

    Institution: 東北大学

    2020/04/01 - 2023/03/31

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    第一に、中性子照射手法の開発を行った。ベルギーBR2を利用して高温・水素雰囲気照射を行うための照射キャプセルを試験するための照射試験チェンバーを作製した。試験チェンバーには電気ヒーター・熱電対・ガスフローシステムなどを設け、試験を精度よく実施可能な構造とした。 第二に、試料を準備した。鉄-クロム2元系合金やF82H等について、微小引張試験片(4×0.25×16 mm3)およびディスク試験片(φ6×0.2 mm3)等を作製した。これら の試料厚さは中性子照射中の水素拡散長よりも十分に小さくした。 第三に、上記試料のミクロ組織観察および昇温脱離分析を行った。ミクロ組織観察は、金研大洗センターに整備されている透過電子顕微鏡(対象:転位組織、クロムリッチ相、粒界偏析/欠乏、炭化物界面)、陽電子消滅測定(対象:空孔、空孔-水素複合体、空孔クラスター、クロムリッチ相)、3次元アトムプロープ(対象:クロムリッチ相、溶質クラスター、粒界偏析/欠乏、炭化物界面)を用いた。さらに、同じく金研大洗センターに整備されている昇温脱離分析装置で、水素蓄積量を定量評価した。その結果をミクロ組織観察の結果と直接比較した。 以上により、【ア】空孔クラスターの形成・成長の促進、【イ】溶質原子拡散の促進または抑制、【ウ】転位組織の形成・発達の促進、【エ】金属水素化物の形成、【オ】炭化物組織の回復の促進等について観察し、電子線照射組織の形成・発達に対する水素効果をそれぞれ調べた。

  6. Advanced negative muon beam development

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research on Innovative Areas (Research in a proposed research area)

    Category: Grant-in-Aid for Scientific Research on Innovative Areas (Research in a proposed research area)

    Institution: High Energy Accelerator Research Organization

    2018/06/29 - 2023/03/31

  7. Control of vacancy concentration and hydrogen isotope retention in neutron-irradiated tungsten alloys for fusion applications

    Hatano Yuji

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (A)

    Category: Grant-in-Aid for Scientific Research (A)

    Institution: University of Toyama

    2018/04/01 - 2022/03/31

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    Future fusion reactors will use deuterium (D) and tritium (T) as fuel and tungsten (W) as a wall material of reactor core. Due to their small sizes, D and T atoms are dissolved into W crystal easily. During reactor operation, W will be irradiated with high energy neutrons produced by fusion reactions, and fine cavities (vacancy and vacancy clusters) are generated in W crystal. These cavities strongly trap D and T atoms and raise T retention in W markedly. Such retention of a large amount of T increases a risk of uncontrolled T release to the environment under accidental conditions. In this study, we systematically investigated irradiation responses of W-Re, -Cr, -Ta and -Mo binary alloys. We found that Re and Cr strongly enhance the annihilation of cavities under irradiation and reduce hydrogen isotope retention in orders of magnitude. The mechanisms underlying such enhanced cavity annihilation was clarified with help of first principle calculation results in literatures.

  8. Measurement of Tritium Distributions on Divertor Tiles used in JET-ITER Like Wall Experiments

    Hatano Yuji

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: University of Toyama

    2014/04 - 2018/03

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    ITER will use Be as a main chamber wall material and W as a divertor material. To examine the performances of these materials in tokamak environment, JET in EU has performed ITER-Like Wall (ILW) experimental campaigns with Be main chamber tiles and W-coated CFC divertor tiles. In this study, tritium (T) distributions on these tiles were examined using imaging plate (IP) technique and beta-ray induced X-ray spectrometry. Two retention mechanisms were found: (1) co-deposition with Be and other impurities, and (2) implantation into material bulk. T concentrations in Be deposition layers were lower than those in carbon deposition layers formed in previous campaigns with carbon tiles. Far less co-deposition of T on the sides of tiles was observed for ILW tiles compared with carbon tiles. Significantly reduced T retention was expected with Be and W walls in comparison with C walls. Technique to measure T retention in an individual dust particle using IP was also developed.

  9. Development of high durable Tungsten materials to realize divertor of a fusion reactor.

    Hasegawa Akira

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (A)

    Category: Grant-in-Aid for Scientific Research (A)

    Institution: Tohoku University

    2012/04/01 - 2017/03/31

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    Divertor is one of component of a fusion reactor to exhaust impurities from plasma. The divertor will be exposed high-flux neutrons, hydrogen ions and high heat load. Tungsten is the most promising candidate material of the divertor component because of its high melting temperature. In this work, we developed new tungsten materials by alloying and controlling fine grain structure to suppress melting and embrittlement, and showed their superior properties compared to conventional tungsten materials by material testing and numerical analysis. Neutron irradiation experiment of these materials was also carried out using a material testing fission reactor in the United States.

  10. Experimental study of discharge plasma fusion neutron source with D-T burning

    Ohnishi Masami, YAMAMOTO Yasushi, OSAWA Hodaka, HATANO Yuuji, MURATA Isao, MASUDA Kai

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Kansai University

    2013/04/01 - 2016/03/31

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    A sealed discharge plasma fusion neutron source facility (IECF) witch secures the tritium safety has been developped for the use of tritium gas. The operation with the D-T mixed gas of the mixture ratio, 93%:7% has achieved 8 times more neutrons than D gas.The multiplication agreed with the theoretical estimation.The use of D-T fuel gas with the mixture of 50%:50% by the discharge voltage 70kV and current 60mA is anticipated to produce ten to the 9th power(1/sec) neutron. The experiments verified the D-T fuel IECF can be a neutron source for radiograph, basic research of the cancer therapy,inspection of explosives and landmine detection etc.

  11. Development of new measurement techniques for application of glow discharge optical emission spectroscopy to plasma-surface interaction studies

    HATANO Yuji, AKAMARU Satoshi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (C)

    Category: Grant-in-Aid for Scientific Research (C)

    Institution: University of Toyama

    2011 - 2013

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    Glow-discharge optical emission spectroscopy (GDOES) allows high resolution and rapid depth profiling of constituent elements in a solid specimen. These features are in principle suitable for the analysis of plasma-facing materials (PFMs) used in fusion devices. There are, however, special requirements for PFM analysis: (1) isotope analysis, (2) quantitative measurement of hydrogen isotopes, (3) helium detection, and (4) influence of hydrogen isotope content on sputtering rate of materials. This study has revealed that (1) resolution of diffraction grating in a commercial GDOES device is sufficiently high to separately detect H and D, (2) thin films of hydrogen absorbing materials are suitable as a standard sample for quantitative analysis of hydrogen isotopes, (3) helium detection is possible using high power, high pressure Ne plasma and (4) there is no significant influence of hydrogen isotope content on sputtering rate of carbon-hydrogen co-deposited films.

  12. Tritium behavior at the interface of oxidized metal under high temperature water

    NAKAMURA Hirofumi, HATANO Yuji, ISOBE Kanetsugu

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (C)

    Category: Grant-in-Aid for Scientific Research (C)

    Institution: Japan Atomic Energy Agency

    2009 - 2011

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    Deuterium behavior into the metals soaked in pressurized high temperature heavy water has been investigated in order to understand the oxidation initiated tritium infiltration in the nuclear reactor such as steel or nickel. Deuterium amount and depth distribution of elements in samples oxidized in hot heavy water were measured by the thermal desorption method and a glow discharge optical elemental spectroscopy method, respectively. As the results, it was found that deuterium infiltration into the material would be initiated by the deuterium gas generated at the oxidation process of metal at the oxide. metal interface. Nickel as the anti corrosion metal and gold plating as the permeation reduction coating could be relatively effective to prevent deuterium infiltration into the metal.

  13. TRITIUM PERMEATION, CONTAMINATION AND DECONTAMINATION

    HATANO Yuji, TORIKAI Yuji, AKAMARU Satoshi, OYA Yasuhisa, ODA Takuji, TANAKA Satoru, NAKAMURA Hirofumi, ASAKURA Yamato

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research on Priority Areas

    Category: Grant-in-Aid for Scientific Research on Priority Areas

    Institution: University of Toyama

    2007 - 2011

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    The objective of this study is to gain an understanding of tritium (T)-material interactions to minimize uncontrolled tritium emissions from fusion reactors. The main chemical forms of T permeating steel pipes are HT and HTO, and the latter has a far higher risk of internal exposure. We found that the fraction of HTO was able to be reduced by reducing surface coverage of Fe hydroxides. Developments of wet-chemical methods to prepare ceramic permeation barrier coatings enabled reduction in permeation rate to 1/104. Retention of T in tungsten being a leading candidate of plasma-facing material was found to increase significantly with neutron irradiations. Important parameters for assessment of T inventory in a reactor core such as binding energy between T and radiation defects were quantitatively evaluated. Heat treatments under the presence of H and/or D were proposed for efficient decontamination of neutron-irradiated tungsten.

  14. Research and development on safety confinement and permeation control of tritium for fusion reactor

    YAMANISHI Toshihiko, HATANO Yuuji, OKUNO Kenji, SUGIYAMA Takahiko, HARA Masanori, NISHIKAWA Masabumi, KOBAYASHI Kaori, KURATA Rie

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research on Priority Areas

    Category: Grant-in-Aid for Scientific Research on Priority Areas

    Institution: Japan Atomic Energy Agency

    2007 - 2011

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    Two workshops were held in a year as a joint workshop of our two R&D groups. A series of discussions on the R&D results and future plans was made in the workshops. Through these workshops, our annual R&D goal was attained in each year. In addition, we have presented our R&D results at many domestic and international conferences. Quite valuable comments have been obtained through the discussions at the conferences to carry out our R&D subjects. We accordingly could make a set of database for the safety of fusion reactors: confinement of tritium; permeation barrier; and safe handling. Our R&D subjects are quite unique from viewpoint of the safety having the interface to the environment. As a typical deliverable of our R&D results, we have agreed to make a tritium handbook in the next fiscal year.

  15. IMRPVEMENT OF HIGH TEMPERATURE DURABILITY OF COMPOSITE HYDROGEN PERMEATION MEMBRANE BY USING CARBIDES AND NITRIDES OF GROUP 4 METALS AS INTERMEDIATE LAYER

    HATANO Yuji, HARA Masanori

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: University of Toyama

    2007 - 2009

  16. Carbides of Group 4 and 5 Metals as Functional Materials for Hydrogen Energy

    HATANO Yuji, HARA Masanori

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (C)

    Category: Grant-in-Aid for Scientific Research (C)

    Institution: University of Toyama

    2005 - 2006

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    Carbides of group 4 and 5 metals have unique physical and chemical properties such as refractoriness, extreme hardness and high chemical stability. Hence, systematic studies on the interactions between these carbides and hydrogen isotopes may lead to the development of new functional materials for handling of hydrogen isotopes. From these viewpoints, hydrogen absorption, desorption, diffusion and permeation were examined for these carbides in the present study. Hydrogen absorption and desorption by powder specimens of TiC and ZrC were examined in the range of temperature 773 to 973 K and H_2 pressure 1 Pa to 50 kPa. Reversible hydrogen absorption-desorption was observed for these carbides, although TiN and ZrN having the same crystal structure as carbides did not react with hydrogen. Such significant difference between carbides and nitrides was ascribed to the presence of carbon vacancy in the former. The equilibrium hydrogen concentration was 0.1-1 mol% in TiC and 0.01 - 0.1 mol% in ZrC under the present conditions; the solubility of hydrogen in the carbides showed much weaker dependence on H_2 pressure than that expected from Sieverts' law. The diffusivity of hydrogen in TiC was also evaluated. The hydrogen permeation through the carbides of group 5 metals was investigated at 573 - 773 K by examining the hydrogen absorption by sheet type specimens of group 5 metals with carbides layers. The thickness of carbide layers ranged 100 nm to several μm. Rapid hydrogen absorption was observed if Pd coating was prepared on the specimen surfaces over the carbide layers, although the absorption rate without Pd coating was significantly smaller. These observations indicated that the carbides of group 5 metals have rather high permeability for hydrogen, although their surfaces are sensitive to poisoning effects by impurities in hydrogen gas such as water vapor.

  17. Development and application in the new method of the surface coating of microparticles, the barrel-sputtering system

    ABE Takayuki, HATANO Yuji, HARA Masanori

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: University of Toyama

    2004 - 2006

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    Powdery materials are available in many industrial materials and products. In order to develop the more attractive powdery materials, surface modification of powdery materials is one of the useful method. However, the conventional method was only the wet process which has some problem such as disposal of waste solution, and limiting of the modified materials. Therefore, a new RF sputtering system installed with a hexagonal-barrel was developed for modifying the surfaces of powdery materials in dry process, named as barrel-sputtering system. The validity of this system was examined for surface coating of metal, ceramics, polymer and ionic crystal powders with different grain shapes and sizes. It was found that the surfaces of powder grains could be uniformly coated with metal, alloys and oxides layers, regardless of their shapes. In addition, the size of powder grains was applicable from several centimeters to several hundred nanometers. Moreover, the form of coating materials was controlled between a thin layer and the nanoparticles. For example to develop the functional powdery materials, the electrochemical catalyst as the usage in the polymer electrolyte fuel cell was prepared by using the system. The carbon black powder modified with Pt-Ru nanoparticles showed the excellent performance in comparison with the catalysts prepared by the conventional wet process.

  18. Construction of the standard system for absolute measurement of tritium

    MATSUYAMA Masao, HATANO Yuji, TORIKAI Yuji, HARA Masanori

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (A)

    Category: Grant-in-Aid for Scientific Research (A)

    Institution: University of Toyama

    2003 - 2005

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    To evaluate the absolute amount of tritium, a calorimetric system was designed and constructed, and its basic performance has been tested. The calorimetric system is applicable to measure solid, liquid and gaseous tritium. For this application the present calorimetric system is equipped with a high sensitivity calorimeter, a tritium container, total pressure gauges, a quadrupole mass spectrometer, and high vacuum systems. A twin type thermal conductivity calorimeter with a vacuum shielding was specially employed for the present purpose. A calibration curve of the calorimeter has been prepared at first using solid materials absorbed a given amount of tritium, and the following linear relation was obtained : E_<out>=(0.2694±0.0010) Q_<in>, where E_<out> describes the output (μV) from the heat sensors and Q_<in> the input power (μW) by Joule heating to the sample cell. In addition, the lower detection limit was estimated to be 0.15μW from stability of the calorimeter, which corresponds to the tritium amount of 0.16 GBq. As the first test, Zr-Ni alloy powder loaded with a given amount of tritium was measured by the calorimeter and the amount of tritium was evaluated to be 26.3 GBq, which was a little lower than the tritium activity determined previously by using a small ionization chamber. The second test was applied to measurement of tritiated water. The observed calorific value was about ten times greater than that of the expected value. It was seen that this is due to the oxidation reaction of a liquid cell with oxygen dissolved into tritiated water. Improvement of a liquid cell will lead to successful measurements of tritium.

  19. Absorption of Hydrogen Isotopes by Vanadium-based Low Activation Materials

    WATANABE Kuniaki, HATANO Yuji, HARA Masanori

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Toyama University

    2002 - 2004

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    Vanadium alloys are potential candidates of low activation structural materials for fusion reactors. Permeability of hydrogen isotopes including tritium, however, is high in these alloys. It is known that the permeation of hydrogen isotopes though group 5 metals sensitively depends on surface states, but the systematic study has not been carried out for these alloys. From this viewpoint, absorption of H_2 and D_2 by V-Ti and V-Ti-Cr alloys was examined in the present study in combination with surface analysis by X-ray photoelectron spectroscopy to understand the correlation between surface chemical states and the reaction rates of hydrogen isotopes. Sheet type specimens of V-4Ti alloy and V-4Ti-4Cr alloy supplied by the National Institute for Fusion Science were installed in an ultra-high vacuum chamber, and their surfaces were analyzed after heat treatments at 673-1273 K. Enrichment of Ti on the surfaces were clearly observed above 800 K for both alloys. The specimens with different surface Ti concentrations were prepared by respective heat treatments, and hydrogen absorption was examined in a temperature range from 523 to 1023 K. The sticking coefficient α on the surface without Ti enrichment was 10^<-3> -10^<-4>, while the surface segregation of Ti up to [Ti]/[V] 〜0.5 led to the reduction in α by 2-3 orders of magnitude. Namely, the surface segregation of Ti caused the barrier effect against hydrogen permeation. The potential barrier against dissociative adsorption of hydrogen evaluated by ab initio calculations showed that direct influence of Ti is negligibly small. It was concluded that the reduction in α was due to the increase in the surface coverage of impurity oxygen caused by the presence of Ti whose chemical affinity to oxygen is larger that of V. The isotope effect between H_2 and D_2 was small and not observable under the present conditions.

  20. 核融合炉ダイバータにおける水素排気用超透過膜の開拓

    波多野 雄治

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 若手研究(A)

    Category: 若手研究(A)

    Institution: 富山大学

    2002 - 2004

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    定常運転核融合炉における周辺粒子制御への応用を目指し、超透過現象を利用したメンブレンポンプの開発が進められている。超透過は、透過膜入射側表面が酸素等の非金属不純物で覆われており、水素同位体の再結合放出が抑制されている場合に発現する。従って、スパッタリング環境下で透過性能を維持するためには、バルク中へ不純物を溶解し連続的に表面偏析させる必要がある。昨年度までに、超透過膜候補材である5族金属の中でも比較的表面状態の制御が容易なNbについて、酸素が支配的な表面偏析元素であることを確認すると共に、水素同位体の表面再結合を酸素が抑制する機構、水素イオンによる偏析酸素のスパッタ率などを調べた。本年度は、中性子照射による誘導放射能が低いという実用上好ましい特性を有するVについて、その特性を評価した。 まず、本研究経費で整備したプラズマ駆動透過実験装置に厚さ0.1mmのV膜を取り付け、バイアス電圧0〜250V、入射イオン流束0.6〜1.2×10^<19>m^2s^<-1>、膜温度703〜823Kでプラズマ駆動実験を行った。表面不純物がスパッタされるような高いバイアス電圧を印加しても透過速度は減少せず、連続的な不純物の表面偏析により、スパッタ環境下でも超透過が維持されることが確認された。上述のように、Nbの場合には酸素が支配的な表面偏析元素であり、バルク中の酸素濃度と水素同位体の表面反応速度との間に明確な相関が見られた。一方、V表面での水素同位体反応速度は、バルク中の酸素濃度のみならず熱処理条件にも敏感に依存し、複雑な変化を示した。表面分析の結果から、この複雑な変化は硫黄の影響によるものであることが示唆された。また、炭素をプラズマ対向材料として使用する炉では、透過膜表面に炭素が堆積し、炭化物層が形成される可能性がある。そこで予備的実験を行い、V炭化物層が水素透過能を有することを確認した。

  21. Tracking of tritium trapped on/in high-Z materials by BIXS

    MATSUYAMA Masao, HARA Masanori, TORIKAI Yuji, HATANO Yuji

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: TOYAMA UNIVERSITY

    2001 - 2002

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    Trap and/or diffusion behavior of tritium in high-Z materials such as W and Mo, which are promising candidate as plasma-facing materials of fusion devices, have been studied by means of β-ray-induced X-ray spectrometry (BIXS). Main results obtained in the present study were as follows : (1) Diffusion behavior of tritium in W at room temperature A given amount of tritium ions was implanted in a tungsten sample, and then change in β-ray-induced X-ray spectra at room temperature was tracked. The X-ray spectra observed were analyzed by means of computer simulation to estimate tritium depth profiles in tungsten. From change in the depth profiles, the diffusion coefficient of tritium at room temperature was estimated to be 2.4x10^<19> m^2/s. (2) Thermal behavior of tritium ions implanted into W The tungsten sample irradiated with tritium was stepwise heated from room temperature to 700℃, and an X-ray spectrum was measured after each heating As a result, both X-ray intensities of Ar and W decreased with the increase of temperature, and they decreased to about 10% of the initial intensity at 500℃, indicating hat most of the implanted tritium desorbed from surface layers and bulk of the sample. (3) Effect of He pre-irradiation on the trap and diffusion behavior of tritium When tritium was implanted into the He pre-irradiation sample, the X-ray intensity of Ar was about 5 times great in comparison with the He non-irradiation sample, and no change in the intensity at room temperature was observed for five months. Namely, it was seen that the retention of tritium strongly increased with the He pre-irradiation. The amount of tritium in surface layers decreased with heating, but that in bulk did not change up to 350℃. This indicates that the implanted tritium was strongly trapped at lattice imperfections formed by the He pre-irradiation, and the trapping energy of tritium was estimated to be about 1.2eV.

  22. Direct Removal of Tritium from Mixture Gas by Alloy Getter with Functional Surfaces

    HATANO Yuji, HARA Masanori, MATSUYAMA Masao, WATANABE Kimiaki

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (C)

    Category: Grant-in-Aid for Scientific Research (C)

    Institution: Toyama University

    2000 - 2001

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    Tritium and deuterium coexist with helium and other impurities in exhaust gas from fusion reactor core. The separation of tritium from He and other gases is important task from the viewpoints of safety assessment and tritium economy. Direct removal of tritium by alloy getters with low equilibrium tritium pressure is safe and efficient method for tritium separation. The efficiency for tritium removal, however, can be degraded by poisoning by impurities such oxygen and carbon. The objective of the present project is to explore the surface modification technique to drastically improve the durability of getters against poisoning. ZrNi was selected as model material. Pd coating was carried out in 2001 with electroless plating technique. Specimen was exposed to argon gas containing H_2O, CO_2 and O_2, and degradation in deuterium absorption rate was examined at temperatures from 373 to 573 K. The durability against poisoning was significantly improved by Pd coating above 473 K. It should be emphasized that no significant degradation was observed for Pd coated specimen at 573 K, whereas the specimen without Pd coating was completely deactivated by 2 h exposure. In 2001, attention was focused on improvement of durability at lower temperatures. Sputter deposition was selected as new Pd coating technique. The activation behavior after exposure to air was examined to investigate the influence of surface impurities on absorption of hydrogen isotopes. The Pd coated specimen was activated by heating in vacuum at 423 K, whereas activation at 873 K was necessary for the specimen without Pd coating. This observation indicated that no stable oxide was formed at the surface of Pd coated specimen by exposure to air at room temperature. So, high durability at low temperature is expected. The mass analyzer purchased was used to analyze impurities in argon, deuterium and hydrogen gases.

  23. KINETIC ISOTOPE EFFECTS ON HYDROGEN ABSORPTION AND DESORPTION BY Pd-ALLOYS

    WATANABE Kuniaki, HATANO Yuhji, MATSUYAMA Masao, ASHIDA Kan

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B).

    Institution: TOYAMA UNIVERSITY

    1998 - 2000

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    The present authors have developed a new type of gas chromatography for separation of hydrogen isotopes. It can be operated near room temperature with any replacement gases by use of a column prepared from powder of Pt-8 at%Pd. It is important, however, to investigate in detail isotope effects on hydrogen absorption and desorption to improve the separation efficiency under much moderate operation conditions. The objective of the present research project is to understand mechanisms of hydrogen absorption and desorption, and to evaluate the kinetic as well as thermodynamic isotope effects. Materials considered in this program were Pt-based alloys : Pt-Pd and Pt-Ni alloys. The kinetics was measured using a vacuum microbalance and the thermodynamic properties of alloys were determined from PCT curves obtained by using a conventional constant volume apparatus. It was found that the rates of hydrogen absorption and desorption were determined by adsorption and desorption on the surface, and diffusion in the bulk, where all of them contribute equally. Then the kinetics was described by a diffusion equations as <<numerical formula>> All of the reaction curves obtained in the present study could be reproduced well by this kinetic model. According to the kinetic analyses, the rate of diffusion were not so fast, about 100 times slower than that in pure Pd. The analyses showed that the rate of protium adsorption on the surface is about 1.5 times greater than that of deuterium, whereas protium desorbs from the surface about 1/2 slower than deuterium. As for the diffusion, deuterium can migrate in the bulk about 2 times faster than protium near room temperature for Pd-4at%Pt alloy. This alloy showed a large thermodynamic isotope effect : the isotope effect defined by a ratio of equilibrium pressures, P_<D_2>/P_<H_2>, was found to be about 5 around room temperature. The present research project reveled that the separation efficiency can be improved much by preparing the separation column from materials having large thermodynamic isotope effects, since the kinetic isotope effects are expected to be relative smaller. In this case, however, the present study also showed that powder particles for the column should be small enough to assure equilibrium conditions. These conclusions can be a guiding principle to improve the newly developed gas chromatograph for hydrogen isotope separation working at room temperature using any replacement gases.

  24. 低放射化バナジウム合金中の水素同位体挙動 Competitive

    System: 科学研究費補助金

    2000 -

  25. 水素透過膜の開発 Competitive

    2000 -

  26. 原子・イオン状水素同位体と金属材料の相互作用 Competitive

    System: 科学研究費補助金

    2000 -

  27. Tritium Behavior in Low-activation Vanadium Alloys Competitive

    System: Grant-in-Aid for Scientific Research

    2000 -

  28. Hydrogen permeation membrane Competitive

    2000 -

  29. Interaction between materials and atomic/ionic hydrogen isotopes Competitive

    System: Grant-in-Aid for Scientific Research

    2000 -

  30. TRITIUM TRAPPING IN MULTI-LAYER PLASMA FACING MATERIALS

    SHU Wei Min, HATANO Yuji, MATSUYAMA Masao, WATANABE Kuniaki, ASHIDA Kan

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (C)

    Institution: TOYAMA UNIVERSITY

    1997 - 1998

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    The permeation and inventory of tritium in a multi-layer divertor were examined under ITER condition by an analytic model taking into account temperature gradient and erosion effect. The erosion accelerated the tritium permeation for both Be/Cu and W/Cu options. Its effect on tritium inventory was, however, significantly different between the former and the latter. In the case of the Be/Cu option1 the tritium inventory in the Be layer dominated the total, and hence the decrease of Be layer thickness due to the erosion resulted in the reduction of the total inventory, In the case of W/Cu option, the tritium inventory gradually decreased initially with the progression of erosion and increased sharply. This distinct behavior was ascribed to the difference in relative magnitude of tritium solubility between Be and Cu, and between W and Cu. The influence of damaged surface layer on the permeation and inventory of hydrogen was also examined experimentally. The upstream surface of a vanadium membrane (0.1 mm in thickness) was exposed to hydrogen gas at 640 Pa and 673 K, and the steady state of the permeation was attained. Then. the downstream surface of the membrane was irradiated with He ions. No significant variation of the permeation rate was observed in the initial stage of irradiation. The permeation rate, however, started to decrease at the fluence of 10^<21> m^<-2> with further irradiation. This was attributed to the trapping effect on hydrogen diffusion by radiation defects. The irradiation of He ions was intermitted when the permeation rate decreased to a half of the initial value, and then the ion beam was switched on and off repeatedly. The permeation rate increased promptly by the switching-on and decreased by the switching-off These results clearly indicated that the trapping effect under irradiation is small compared with that in the absence of irradiation.

  31. Development of the bremsstrahlung counting method for in-situ measurements of tritium absorbed into materials.

    MATSUYAMA Masao, HATANO Yuji, SHU Wei Min, ASHIDA Kan, WATANABE Kuniaki

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: TOYAMA UNIVERSITY

    1996 - 1998

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    Research and development of techniques to lower tritium inventory in a fuel cycle is indispensable for the establishment of a thermonuclear fusion reactor. For this purpose, it is necessary to develop the techniques to measure in-situ and nondestructively the amount and the depth profile of tritium dissolved into materials. From this viewpoint, (i) correlation between a depth profile of tritium and a bremsstrahlung x-ray spectrum and (ii) analysis of a bremsstrahlung x-ray spectrum with a computer simulation have been examined in the present study. First of all, a simulation program has been developed to evaluate the tritium depth profiles in materials from analyses of a bremsstrahlung x-ray spectrum by means of a computer simulation. To examine validity of the developed program, a bremsstrahlung x-ray spectrum was measured using an organic polymer material labeled uniformly with tritium as a model material, and it was compared with the spectrum obtained by a computer simulation. As a result, it was seen that the spectrum obtained from the simulation agreed quite well with that observed by measurements, and for acrylic resin mainly consisting of low-Z elements such as carbon, it was confirmed that it is possible to measure tritium which exist in the depth from the surface to about 1mm. From those results, it was revealed that the developed simulation program is valuable for the analyses of a bremsstrahlung x-ray spectrum emitted from the materials containing tritium. After these experiments, applicability of the present method to the metallic materials such as Pd, Zr and ZrNi having a non-uniform depth profile of tritium was examined. In these materials a characteristic x-ray spectrum was observed along with a bremsstrahlung x-ray spectrum, and the simulation program mentioned above, therefore, was improved to analyze a complex spectrum consisting of two kinds of x-ray spectrum. It was seen that the improved program is thoroughly applicable to reproduction of the complex spectra. Accordingly, it was concluded that the present method is quite useful for in-situ and nondestructive measurements of a tritium depth profile for metallic materials constituted of multi-components.

  32. トリチウムの安全取扱い技術に関する研究 Competitive

    System: 国際共同研究

    1998 -

  33. Study on Tritium Handling Competitive

    1998 -

  34. 5族金属中のトリチウムの拡散と水素同位体間の動的相関

    杉崎 昌和, 波多野 雄治, 橋爪 健一

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 重点領域研究

    Category: 重点領域研究

    Institution: 九州大学

    1997 - 1997

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    5族金属中における水素同位体の拡散が量子トンネル効果に基づくものであることは良く知られているが、このような場合に異種の同位体を混合したら、拡散係数がどのように変化するかということは非常に興味深い問題である。本研究ではこのような観点から、5族金属中にトリチウムと軽水素もしくは重水素を溶解した系におけるトリチウムのトレーサー拡散係数を測定し、共存する同位体の種類によりトリチウムのトレーサー拡散係数が変化するかどうかを調べた。測定はバナジウム、ニオブ、タンタルについて行った。トリチウムのトレーサー拡散係数の測定にあたっては、当研究グループが開発したグロー放電注入法を用いた。実験で用いた試料の純度は約99.9%、形状は直径5mm、長さ50mmである。先ず、試料に軽水素もしくは重水素を所定の濃度均一に溶解しておき、試料の一端面をトリチウムガスのグロー放電プラズマに曝し、ごく微量のトリチウムを試料端面に注入する。トリチウムの拡散実験は250℃で行った。 実験により得られたトリチウムの拡散係数は共存する同位体の濃度により著しく変化し、濃度が大きくなるに従い減少する傾向を示した。また、重水素中より軽水素中の方がわずかに大きくなる傾向を示した。この同位体の種類による違いはトリチウムと共存する水素同位体間の動的相関によるものであると考えられる。なお、今後このトリチウムのトレーサー拡散係数の温度依存性を測定し、量子トンネル効果の機構を研究して行く予定である。なお、この研究成果の一部はInternational Conference of Fusion Reactor Materials(ICFRM-8,Sendai,October1997)において発表した。論文タイトルは「Influence of coexisting hydrogen isotopes on diffusion of tritium in niobium」である。

  35. 非化学量論性金属酸化物中への水素の溶解挙動と電子物性に与える影響

    波多野 雄治

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 奨励研究(A)

    Category: 奨励研究(A)

    Institution: 九州大学

    1996 - 1996

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    高純度ジルコニウム(クリスタルバ-)の板状試料を673Kにおいて0.1MPaの水蒸気または重水水蒸気中で10時間酸化させることにより、水素または重水素を約1mol%含んだ厚さ約800nmの緻密なジルコニア被膜を形成させた。また、同様の温度・圧力の酸素ガス中で60時間酸化させることにより、同様の厚さの水素を含まないジルコニア被膜を形成させた。 水素のジルコニア中での化学状態を調べるため、それぞれの被膜について高感度反射法により赤外吸収スペクトルを測定した。波数領域650〜850cm^<-1>のスペクトルに(重)水素を含む被膜と含まない被膜との間に顕著な違いが見られ、(重)水素を含む被膜でのみ810cm^<-1>に大きなピークが観察された。また、軽水素を含む被膜と重水素を含む被膜との間には、スペクトルに差異は見られなかった。このことから、810cm^<-1>のピークは水素自身の振動に起因するのではなく、水素が溶解することによりジルコニアの格子振動の状態が著しく変化したことに起因していることがわかった。なお、O-HおよびO-Dの振動に起因するピークは観察されず、水素は緻密なジルコニア中ではO-H、O-Dとしては存在していないことがわかった。 水素の溶解がジルコニアの電子物性に及ぼす影響を調べるため、水素を含む被膜と含まない被膜について、X線光電子分光法を用いて価電子帯における電子の状態密度分布を測定すると共に、ケルビン法により仕事関数を測定した。価電子帯の状態密度分布には水素の溶解による顕著な変化は見られなかったが、仕事関数については水素を含む被膜の方が大きな値を示す傾向が見られた。これらの結果は、水素が溶解することによりジルコニアのフェルミ準位およびバンドギャップが変化していることを示唆している。

  36. ESTIMATION OF HYDROGEN REDISTRIBUTION IN ZIRCALOY CLADDING OF SPENT FUEL DURING DRY STORAGE AND ITS INFLUENCE ON MECHANICAL PROPERTIES OF CLADDING

    SUGISAKI Masayasu, HATANO Yuji, HASHIZUME Kenichi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Developmental Scientific Research (B)

    Category: Grant-in-Aid for Developmental Scientific Research (B)

    Institution: KYUSHU UNIVERSITY

    1994 - 1995

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    The toughness of Ziraloy-2 specimens (size : 5mm x 10mm x 50mm) containing 100 ppm or 400 ppm hydrogen was measured with the Charpy test in a temperature region from room temperature to 250゚C.The hydrogen concentration in the specimens was gradient in one dimension, which was prepared with the thermomigration of hydrogen. The measurement suggested that the toughness of the specimen, in which the hydride is nonuniformly distributed, was larger than that of the specimen in which the hydride was uniformly distributed. The redistribution phenomena of hydride in the Zircaloy cladding of the fuel for the light water cooled reactors under the conditions of the dry storage was analyzed from the thermodynamical aspect and the rate of redistribution of the hydride was calculated with the computer simulation, in which the burn-up of the fuel was assumed as 40-55Gwd/t and the amount of hydrogen absorbed in the cladding was also assumed as 300-400ppm. In the calculation, the temperature conditions of the dry storage was assumed as 150-450゚C.Followings were concluded : (1) The nonuniform distribution of the hydride in the radial direction of the Zircaloy claddings, which was brought about in the reactors, would not be relaxd under the designed temperature conditions of the dry storage. (2) In the case of the dry storage of the spent fuel with the Zircaloy cladding containing 400 ppm hydrogen, the nonuniform distribution of the hydride in the Zircaloy cladding would be collapsed and uniform distribution of the hydride would be built up in an hour provided that the temperature of the Zircaloy cladding would be increased over 480゚C because of certain accidents. This redistribution of the hydride would bring about the marked decrease of the toughness of the Zircaloy cladding. These results were presented in the meeting of International Atomic Energy Agency and in the Fall Meeting of Nihon Genshiryoku Gakkai.

  37. Tritium Inventory in Fuel Element of Light Water Reactor and Release Mechanism of Tritium to Reactor Coolant

    SUGISAKI Masayasu, HATANO Yuji, HASHIZUME Kenichi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for General Scientific Research (B)

    Category: Grant-in-Aid for General Scientific Research (B)

    Institution: KYUSHU UNIVERSITY

    1990 - 1992

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    The release mechanisms of tritium produced by ternary fission of uranium to reactor coolant were experimentally examined. In particular, the influences of following three elementary processes were considered; (1)Influence of thermal gradient upon the diffusion of tritium in the zircaloy cladding was examined by carrying out the thermo-migration experiment of tritium and protiumin zirconium. (2)Interaction of tritium diffusion with that of protium originated from the oxidation of cladding materials with high temperature and pressure cooling water was examined on the basis of the oxidation experiment of zircaloy with high temperature steam,in which dissolution mechanism of hydrogen originated from the reduction of water was quantitatively examined. (3)For examination of the influence of oxygen dissolved in zircaloy upon the diffusion of tritium, a new type exeprimental method to measure the diffusion coefficient of hydrogen isotopes was developed, which is based on the implantation technique of hydrogen isotopes into the specimen surface by making use of glow-discharge of hydrogen gas.

  38. 水素同位体の吸着・表面拡散・再結合脱離に及ぼす表面不純物の影響 Competitive

  39. セラミックス材料中の水素挙動 Competitive

  40. トリチウムオートラジオグラフ法・イメージングプレート法による水素脆化機構の研究 Competitive

  41. 高性能水素透過膜の開発 Competitive

  42. Hydrogen behavior in ceramic materials Competitive

  43. Influence of surface impurities on absorption, diffusion and recombinative desorption on metal surfaces. Competitive

  44. Study on hydrogen embrittlement mechanism by use of tritium autoradiography and imaging plate Competitive

  45. Development of new hydrogen permeation membrane Competitive

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Teaching Experience 8

  1. Advanced Energy Physics Engineering Tohoku University

  2. 科学と社会 富山大学

  3. 富山から考える震災・復興学 富山大学

  4. Advanced Radiation Chemistry University of Toyama

  5. Introduction to Radiochemistry University of Toyama

  6. Fusion Reactor Materials Science University of Toyama

  7. 機能性材料学 富山大学

  8. Materials Science University of Toyama

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