Details of the Researcher

PHOTO

Kiyohiro Yabuuchi
Section
Institute for Materials Research
Job title
Associate Professor
Degree
  • 博士(エネルギー科学)(京都大学)

  • 修士(エネルギー科学)(京都大学)

Research History 7

  • 2025/04 - Present
    Tohoku University Institute for Materials Research Assistant Professor

  • 2014/12 - 2025/03
    Kyoto University Institute of Advanced Energy Assistant Professor

  • 2016/02 - 2017/01
    JSPS Overseas Research Fellow

  • 2012/04 - 2014/11
    Tohoku University Graduate School of Engineering Assistant Professor

  • 2011/10 - 2012/03
    JSPS Research Fellow PD

  • 2009/04 - 2011/09
    JSPS Research Fellow DC1

  • 2007/04 - 2009/03
    Mitsubishi Electric Corporation

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Education 3

  • Kyoto University Graduate School of Energy Science

    2009/04 - 2011/09

  • Kyoto University Graduate School of Energy Science

    2005/04 - 2007/03

  • Kyoto University Graduate School of Engineering Engineering Science

    2001/04 - 2005/03

Professional Memberships 3

  • 日本金属学会

  • 日本原子力学会

  • 日本鉄鋼協会

Research Areas 4

  • Energy / Nuclear fusion /

  • Energy / Nuclear engineering /

  • Nanotechnology/Materials / Structural and functional materials /

  • Nanotechnology/Materials / Metallic materials /

Awards 5

  1. NuMat2012 Young Scientist Poster Award

    2012

  2. 日本原子力学会材料部会 奨励賞

    2011

  3. 日本金属学会2011年秋季大会 優秀ポスター賞

    2011

  4. 日本原子力学会関西支部若手研究発表会 優秀発表賞

    2011

  5. 第8回核融合エネルギー連合講演会 若手優秀発表賞

    2010

Papers 86

  1. Ion-mixing-induced mitigation of swelling and modulus reduction in irradiated SiC fibers

    Xinwei Yuan, Sosuke Kondo, Diancheng Geng, Kiyohiro Yabuuchi, Hao Yu, Yasuyuki Ogino, Ryuta Kasada

    Journal of the European Ceramic Society 2025/11

    DOI: 10.1016/j.jeurceramsoc.2025.117563  

  2. Helium plasma-induced surface modifications of unirradiated and pre-ion irradiated tungsten at LHD divertor leg position

    Kiyohiro Yabuuchi

    Nuclear Fusion 2025

    DOI: 10.1088/1741-4326/ADB983  

  3. Surface modifications on unirradiated and ion-irradiated tungsten after exposed to deuterium plasma at LHD divertor-leg position

    Kiyohiro Yabuuchi

    Nuclear Fusion 2025

    DOI: 10.1088/1741-4326/ADB862  

  4. Effects of irradiation on interfacial strength and microstructure of double-layer mullite and alumina coating on SiC

    Taichi Miyagishi, Sosuke Kondo, Hirokazu Katsui, Kiyohiro Yabuuchi, Ryutaro Usukawa, Yasuyuki Ogino, Hao Yu, Ryuta Kasada

    Journal of Nuclear Materials 603 155410-155410 2025/01

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2024.155410  

    ISSN: 0022-3115

  5. Irradiation effects on copper oxide superconductors including high-entropy REBCO(HE-REBCO) Peer-reviewed

    Kota Sakurai, Aichi Yamashita, Yoshikazu Mizuguchi, Kiyohiro Yabuuchi, Naoko Oono-Hori

    Nuclear Materials and Energy 40 101709-101709 2024/09

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2024.101709  

    ISSN: 2352-1791

  6. Microstructure evolution of γ-Al2O3/FeAl tritium permeation barrier coatings under 6.4 MeV Fe3+ ion irradiation

    Fengcheng Liu, Hucheng Yu, Xiaoou Yi, Shunjie Deng, Shulei Li, Kiyohiro Yabuuchi, Somei Ohnuki

    Nuclear Materials and Energy 38 101627-101627 2024/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2024.101627  

    ISSN: 2352-1791

    eISSN: 2352-1791

  7. Thermal annealing effect on D retention for damaged W-10%Re alloy

    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

  8. Ultrahigh-Flux Concerting Materials

    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

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

    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 & Design 229 111899-111899 2023/05

    Publisher: Elsevier BV

    DOI: 10.1016/j.matdes.2023.111899  

    ISSN: 0264-1275

  10. Effects of grain boundary volume fraction on the threshold dose of irradiation-induced SiC amorphization at 30 °C Peer-reviewed

    Xinwei Yuan, Sosuke Kondo, Kiyohiro Yabuuchi, Hao Yu, Yasuyuki Ogino, Ryuta Kasada

    Journal of the European Ceramic Society 43 (12) 5125-5135 2023/04

    DOI: 10.1016/j.jeurceramsoc.2023.04.042  

    ISSN: 0955-2219

    eISSN: 1873-619X

  11. Cavity evolution and void swelling in dual ion irradiated tempered martensitic steels

    Takuya Yamamoto, Yuan Wu, Kiyohiro Yabuuchi, Jack Haley, Kenta Yoshida, Akihiko Kimura, G. Robert Odette

    Journal of Nuclear Materials 576 154201-154201 2023/04

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2022.154201  

    ISSN: 0022-3115

  12. Twofold age-hardening mechanism of Al-added high-Cr ODS ferritic steels

    Akihiko Kimura, Wei Sang, Wentuo Han, Kiyohiro Yabuuchi, Zongxi Xin, Junhua Luan, Peng Dou

    Journal of Nuclear Materials 575 154223-154223 2023/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2022.154223  

    ISSN: 0022-3115

  13. Microstructural evolution in tungsten binary alloys under proton and self-ion irradiations at 800 °C

    Takeshi Miyazawa, Yuta Kikuchi, Masami Ando, Ju-Hyeon Yu, Kiyohiro Yabuuchi, Takashi Nozawa, Hiroyasu Tanigawa, Shuhei Nogami, Akira Hasegawa

    Journal of Nuclear Materials 575 154239-154239 2023/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2023.154239  

    ISSN: 0022-3115

  14. Interaction between an edge dislocation and faceted voids in body-centered cubic Fe Peer-reviewed

    Kiyohiro Yabuuchi, Tomoaki Suzudo

    Journal of Nuclear Materials 574 154161-154161 2023/02

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2022.154161  

    ISSN: 0022-3115

  15. Insights into hardening, plastically deformed zone and geometrically necessary dislocations of two ion-irradiated FeCrAl(Zr)-ODS ferritic steels: A combined experimental and simulation study

    Peng Song, Kiyohiro Yabuuchi, Philippe Spätig

    Acta Materialia 234 117991-117991 2022/08

    Publisher: Elsevier BV

    DOI: 10.1016/j.actamat.2022.117991  

    ISSN: 1359-6454

  16. Tungsten–tantalum alloys for fusion reactor applications

    Shuhei Nogami, Itsuki Ozawa, Daisuke Asami, Naoya Matsuta, Seiji Nakabayashi, Siegfried Baumgärtner, Philipp Lied, Kiyohiro Yabuuchi, Takeshi Miyazawa, Yuta Kikuchi, Marius Wirtz, Michael Rieth, Akira Hasegawa

    Journal of Nuclear Materials 566 153740-153740 2022/08

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2022.153740  

    ISSN: 0022-3115

  17. Change in nanoindentation hardness of polycrystalline tungsten irradiated with Fe ions or electrons by hydrogen gas charging

    Koichi Sato, Ryuta Kasada, Atsushi Kiyohara, Masashi Hirabaru, Kenichi Nakano, Kiyohiro Yabuuchi, Masahiko Hatakeyama, Qiu Xu

    Journal of Nuclear Materials 560 153483-153483 2022/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2021.153483  

    ISSN: 0022-3115

  18. Dynamic Interaction between Dislocation and Irradiation-Induced Defects in Stainless Steels during Tensile Deformation

    Kiyohiro Yabuuchi

    Metals 2022

    DOI: 10.3390/MET12050762  

  19. Dynamic interaction between the dislocations and cavities in tungsten during tensile test

    Kiyohiro Yabuuchi

    Nuclear Materials and Energy 2022

    DOI: 10.1016/J.NME.2022.101130  

  20. Radiation embrittlement of clad-HAZ of RPV of a decommissioned BWR plant

    Hideki Yuya, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 557 153300-153300 2021/12

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2021.153300  

    ISSN: 0022-3115

  21. An approximate in-situ method for investigating irradiation damage of grain boundary

    Lei Zhang, Yufeng Du, Wentuo Han, Pingping Liu, Xiaoou Yi, Kiyohiro Yabuuchi, Somei Ohnuki, Farong Wan

    Nuclear Materials and Energy 29 101056-101056 2021/12

    DOI: 10.1016/j.nme.2021.101056  

    ISSN: 2352-1791

    eISSN: 2352-1791

  22. Heavy-ion irradiation and post-irradiation annealing effects in explosion-welded CuCrZr/316LN joints for ITER application

    Xiaoou Yi, Yufeng Du, Diancheng Geng, Zihao Li, Wentuo Han, Pingping Liu, Jiming Chen, Kiyohiro Yabuuchi, Kenta Yoshida, Somei Ohnuki, Qian Zhan, Farong Wan, Yasuyoshi Nagai

    Materials Characterization 178 111252-111252 2021/08

    Publisher: Elsevier BV

    DOI: 10.1016/j.matchar.2021.111252  

    ISSN: 1044-5803

  23. Microstructure and mechanical properties of HAZ of RPVS clad with duplex stainless steel

    Hideki Yuya, Ryoya Kobayashi, Kohei Otomo, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 545 152756-152756 2021/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2020.152756  

    ISSN: 0022-3115

  24. Evaluation of irradiation hardening in ODS-Cu and non ODS-Cu by nanoindentation hardness test and micro-pillar compression test after self-ion irradiation

    Yuchen Liu, Sosuke Kondo, Hao Yu, Kiyohiro Yabuuchi, Ryuta Kasada

    Nuclear Materials and Energy 26 100903-100903 2021/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2021.100903  

    ISSN: 2352-1791

    eISSN: 2352-1791

  25. Irradiation hardening of stainless steel model alloy after Fe-ion irradiation and post-irradiation annealing treatment

    Kiyohiro Yabuuchi

    Journal of Nuclear Materials 2021

    DOI: 10.1016/J.JNUCMAT.2021.153296  

  26. On the use of charged particles to characterize precipitation in irradiated reactor pressure vessel steels with a wide range of compositions

    N. Almirall, P.B. Wells, T. Yamamoto, K. Yabuuchi, A. Kimura, G.R. Odette

    Journal of Nuclear Materials 536 152173-152173 2020/08

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2020.152173  

    ISSN: 0022-3115

  27. Effects of helium implantation with heavy ion irradiation on deuterium permeation in yttrium oxide coating

    Kazuki Nakamura, Hikari Fujita, Jan Engels, Masayuki Tokitani, Yoshimitsu Hishinuma, Kiyohiro Yabuuchi, Sho Kano, Takayuki Terai, Wataru Inami, Yoshimasa Kawata, Takumi Chikada

    Journal of Nuclear Materials 537 152244-152244 2020/08

    DOI: 10.1016/j.jnucmat.2020.152244  

    ISSN: 0022-3115

    eISSN: 1873-4820

  28. Statistical Approach for Understanding the Effect of Specimen Size on the Yield Stress and Its Scattering in Mechanically-Alloyed Cu and ODS-Cu Obtained by Micro-Pillar Compression Test

    Yuchen Liu, Sosuke Kondo, Hao Yu, Kiyohiro Yabuuchi, Ryuta Kasada

    MATERIALS TRANSACTIONS 61 (5) 955-962 2020/05/01

    Publisher: Japan Institute of Metals

    DOI: 10.2320/matertrans.mt-mbw2019005  

    ISSN: 1345-9678

    eISSN: 1347-5320

  29. Assessment of phase stability of oxide particles in different types of 15Cr-ODS ferritic steels under 6.4 MeV Fe ion irradiation at 200 °C

    Peng Song, Akihiko Kimura, Kiyohiro Yabuuchi, Peng Dou, Hideo Watanabe, Jin Gao, Yen-Jui Huang

    Journal of Nuclear Materials 529 151953-151953 2020/02

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2019.151953  

    ISSN: 0022-3115

  30. The stability of γ′ precipitates in a multi-component FeCoNiCrTi0.2 alloy under elevated-temperature irradiation

    Kiyohiro Yabuuchi

    Journal of Nuclear Materials 2020

    DOI: 10.1016/J.JNUCMAT.2020.152364  

  31. Dose dependence of ion irradiation effects on 12Cr–6Al-ODS steel with electron-beam weld line

    Jin Gao, Yuuki Yamasaki, Peng Song, Yen-Jui Huang, Kiyohiro Yabuuchi, Akihiko Kimura, Kan Sakamoto, Shinichiro Yamashita

    Journal of Nuclear Materials 528 151858-151858 2020/01

    DOI: 10.1016/j.jnucmat.2019.151858  

    ISSN: 0022-3115

    eISSN: 1873-4820

  32. Effects of neutron irradiation on 12Cr–6Al-ODS steel with electron-beam weld line

    Jin Gao, Peng Song, Yen-Jui Huang, Kiyohiro Yabuuchi, Akihiko Kimura, Kan Sakamoto, Shinichiro Yamashita

    Journal of Nuclear Materials 524 1-8 2019/10

    DOI: 10.1016/j.jnucmat.2019.06.028  

    ISSN: 0022-3115

    eISSN: 1873-4820

  33. Valence Electron and Chemical State Analysis of Be12M (M = Ti, V) Beryllides by Soft X-ray Emission Spectroscopy

    Keisuke Mukai, Ryuta Kasada, Kiyohiro Yabuuchi, Satoshi Konishi, Jae-Hwan Kim, Masaru. Nakamichi

    ACS Applied Energy Materials 2 (4) 2889-2895 2019/03/07

    Publisher: American Chemical Society (ACS)

    DOI: 10.1021/acsaem.9b00223  

    ISSN: 2574-0962

    eISSN: 2574-0962

  34. Ion-irradiation hardening and microstructural evolution in F82H and ferritic alloys

    Jin Gao, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 515 294-302 2019/03/01

    Publisher: Elsevier B.V.

    DOI: 10.1016/j.jnucmat.2018.12.047  

    ISSN: 0022-3115

  35. Characterization of ordered dislocation loop raft in Fe3+ irradiated pure iron at 300 °C

    Jin Gao, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 511 304-311 2018/12/01

    Publisher: Elsevier {BV}

    DOI: 10.1016/j.jnucmat.2018.09.020  

    ISSN: 0022-3115

  36. Investigation of mechanical properties of stress-relieved and electron-irradiated tungsten after hydrogen charging

    K. Sato, H. Yamashita, A. Hirosako, S. Komazaki, Q. Xu, M. Onoue, R. Kasada, K. Yabuuchi, A. Kimura

    Nuclear Materials and Energy 17 29-33 2018/12

    DOI: 10.1016/j.nme.2018.08.003  

    eISSN: 2352-1791

  37. Ion-irradiation hardening accompanied by irradiation-induced dissolution of oxides in FeCr(Y, Ti)-ODS ferritic steel

    Peng Song, Jin Gao, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 511 200-211 2018/12/01

    Publisher: Elsevier {BV}

    DOI: 10.1016/j.jnucmat.2018.09.007  

    ISSN: 0022-3115

  38. Joint inhomogeneity in dissimilar friction stir welded martensitic and nanostructured ferritic steels

    Wentuo Han, Farong Wan, Kiyohiro Yabuuchi, Hisashi Serizawa, Akihiko Kimura

    Science and Technology of Welding and Joining 23 (8) 659-665 2018/11/01

    Publisher: SAGE Publications

    DOI: 10.1080/13621718.2018.1456797  

    ISSN: 1362-1718

    eISSN: 1743-2936

  39. Tensile properties of mechanically alloyed Zr added austenitic stainless steel

    Daniel Morrall, Jin Gao, Zhexian Zhang, Kiyohiro Yabuuchi, Akihiko Kimura, Takahiro Ishizaki, Yusaku Maruno

    Nuclear Materials and Energy 15 92-96 2018/05/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.nme.2018.03.002  

    ISSN: 2352-1791

  40. Cavity evolution and hardness changes in a 15Cr-ODS ferritic steel by post He-implantation annealing

    Peng Song, Kiyohiro Yabuuchi, Akihiko Kimura

    Nuclear Materials and Energy 15 115-121 2018/05/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.nme.2018.03.006  

    ISSN: 2352-1791

  41. Radiation response of ODS ferritic steels with different oxide particles under ion-irradiation at 550 °C

    Peng Song, Daniel Morrall, Zhexian Zhang, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 502 76-85 2018/04/15

    Publisher: Elsevier B.V.

    DOI: 10.1016/j.jnucmat.2018.02.007  

    ISSN: 0022-3115

  42. Impact of friction stir welding on recrystallization of oxide dispersion strengthened ferritic steel

    Wentuo Han, Pingping Liu, Xiaoou Yi, Qian Zhan, Farong Wan, Kiyohiro Yabuuchi, Hisashi Serizawa, Akihiko Kimura

    Journal of Materials Science & Technology 34 (1) 209-213 2018/01

    Publisher: Elsevier BV

    DOI: 10.1016/j.jmst.2017.11.032  

    ISSN: 1005-0302

  43. Development of high irradiation resistant and corrosion resistant oxide dispersion strengthened austenitic stainless steels

    Takahiro Ishizaki, Yusaku Maruno, Kiyohiro Yabuuchi, Sosuke Kondo, Akihiko Kimura

    Minerals, Metals and Materials Series 9 605-615 2018

    Publisher: Springer International Publishing

    DOI: 10.1007/978-3-319-67244-1_39  

    ISSN: 2367-1696 2367-1181

    eISSN: 2367-1696

  44. Deuterium permeation behavior and its iron-ion irradiation effect in yttrium oxide coating deposited by magnetron sputtering

    Takumi Chikada, Hikari Fujita, Jan Engels, Anne Houben, Jumpei Mochizuki, Seira Horikoshi, Moeki Matsunaga, Masayuki Tokitani, Yoshimitsu Hishinuma, Sosuke Kondo, Kiyohiro Yabuuchi, Thomas Schwarz-Selinger, Takayuki Terai, Yasuhisa Oya

    Journal of Nuclear Materials 511 560-566 2018

    Publisher: Elsevier B.V.

    DOI: 10.1016/j.jnucmat.2018.06.008  

    ISSN: 0022-3115

  45. Application of small specimen test technique to evaluate fracture toughness of reduced activation ferritic/martensitic steel

    Wentuo Han, Kiyohiro Yabuuchi, Ryuta Kasada, Akihiko Kimura, Eiichi Wakai, Hiroyasu Tanigawa, Pingping Liu, Xiaoou Yi, Farong Wan

    Fusion Engineering and Design 125 326-329 2017/12

    DOI: 10.1016/j.fusengdes.2017.01.040  

    ISSN: 0920-3796

  46. Helium bubble formation behavior in ODS ferritic steels with and without simultaneous addition of Al and Zr

    Peng Song, Zhexian Zhang, Kiyohiro Yabuuchi, Akihiko Kimura

    Fusion Engineering and Design 125 396-401 2017/12/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.fusengdes.2017.03.139  

    ISSN: 0920-3796

  47. Deuterium permeation behavior in iron-irradiated erbium oxide coating

    Takumi Chikada, Hikari Fujita, Moeki Matsunaga, Seira Horikoshi, Jumpei Mochizuki, Cui Hu, Freimut Koch, Masayuki Tokitani, Yoshimitsu Hishinuma, Kiyohiro Yabuuchi, Yasuhisa Oya

    Fusion Engineering and Design 124 915-918 2017/11/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.fusengdes.2017.01.016  

    ISSN: 0920-3796

  48. Effect of displacement damage level on the ion-irradiation affected zone evolution in W single crystals

    Eva Hasenhuetl, Zhexian Zhang, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 495 314-321 2017/11

    DOI: 10.1016/j.jnucmat.2017.08.030  

    ISSN: 0022-3115

    eISSN: 1873-4820

  49. Crystal orientation dependence of ion-irradiation hardening in pure tungsten

    Eva Hasenhuetl, Zhexian Zhang, Kiyohiro Yabuuchi, Peng Song, Akihiko Kimura

    Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 397 11-14 2017/04

    DOI: 10.1016/j.nimb.2017.02.030  

    ISSN: 0168-583X

    eISSN: 1872-9584

  50. Evaluation of Ion-Irradiation Hardening of Tungsten Single Crystals by Nanoindentation Technique Considering Material Pile-Up Effect

    Eva Hasenhuetl, Ryuta Kasada, Zhexian Zhang, Kiyohiro Yabuuchi, Yen-Jui Huang, Akihiko Kimura

    MATERIALS TRANSACTIONS 58 (5) 749-756 2017

    DOI: 10.2320/matertrans.m2016437  

    ISSN: 1345-9678

    eISSN: 1347-5320

  51. Ion-Irradiation Effect on Strain Rate Sensitivity of Nanoindentation Hardness of W Single Crystal

    Eva Hasenhuetil, Ryuta Kasada, Zhexian Zhang, Kiyohiro Yabuuchi, Akihiko Kimura

    MATERIALS TRANSACTIONS 58 (4) 580-586 2017

    DOI: 10.2320/matertrans.ML201603  

    ISSN: 1345-9678

    eISSN: 1347-5320

  52. Effect of self-ion irradiation on hardening and microstructure of tungsten

    T. Hwang, M. Fukuda, S. Nogami, A. Hasegawa, H. Usami, K. Yabuuchi, K. Ozawa, H. Tanigawa

    Nuclear Materials and Energy 9 430-435 2016/12/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.nme.2016.06.005  

    ISSN: 2352-1791

    eISSN: 2352-1791

  53. Effect of Cr/Al contents on the 475ºC age-hardening in oxide dispersion strengthened ferritic steels

    Wentuo Han, Kiyohiro Yabuuchi, Akihiko Kimura, Shigeharu Ukai, Naoko Oono, Takeji Kaito, Tadahiko Torimaru, Shigenari Hayashi

    Nuclear Materials and Energy 9 610-615 2016/12/01

    DOI: 10.1016/j.nme.2016.05.015  

    eISSN: 2352-1791

  54. Evaluation of helium effect on ion-irradiation hardening in pure tungsten by nano-indentation method

    Zhexian Zhang, Eva Hasenhuetl, Kiyohiro Yabuuchi, Akihiko Kimura

    Nuclear Materials and Energy 9 539-546 2016/12/01

    Publisher: Elsevier Ltd

    DOI: 10.1016/j.nme.2016.06.010  

    ISSN: 2352-1791

  55. Defect distribution in ion-irradiated pure tungsten at different temperatures

    Zhexian Zhang, Kiyohiro Yabuuchi, Akihiko Kimura

    Journal of Nuclear Materials 480 207-215 2016/11

    DOI: 10.1016/j.jnucmat.2016.08.029  

    ISSN: 0022-3115

    eISSN: 1873-4820

  56. Neutron irradiation effects on the microstructural development of tungsten and tungsten alloys

    Akira Hasegawa, Makoto Fukuda, Kiyohiro Yabuuchi, Shuhei Nogami

    Journal of Nuclear Materials 471 175-183 2016/04

    DOI: 10.1016/j.jnucmat.2015.10.047  

    ISSN: 0022-3115

    eISSN: 1873-4820

  57. The effect of voids on the hardening of body-centered cubic Fe

    Ryosuke Nakai, Kiyohiro Yabuuchi, Shuhei Nogami, Akira Hasegawa

    Journal of Nuclear Materials 471 233-238 2016/04

    DOI: 10.1016/j.jnucmat.2015.09.048  

    ISSN: 0022-3115

    eISSN: 1873-4820

  58. Plastic deformation behavior and bonding strength of an EBW joint between 9Cr-ODS and JLF-1 estimated by symmetric four-point bend tests combined with FEM analysis

    Haiying Fu, Takuya Nagasaka, Takeo Muroga, Wenhai Guan, Shuhei Nogami, Hisashi Serizawa, Shaofei Geng, Kiyohiro Yabuuchi, Akihiko Kimura

    Fusion Engineering and Design 102 88-93 2016/01

    DOI: 10.1016/j.fusengdes.2015.11.037  

    ISSN: 0920-3796

    eISSN: 1873-7196

  59. Oxide Dispersion Strengthened Steels for Advanced Blanket Systems

    Akihiko KIMURA, Wentuo HAN, Hwanil JE, Kiyohiro YABUUCHI, Ryuta KASADA

    Plasma and Fusion Research 11 2505090-2505090 2016

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.11.2505090  

    eISSN: 1880-6821

  60. Anisotropy in the mechanical properties of potassium and rhenium doped tungsten alloy plates for fusion reactor application

    Makoto Fukuda, Shuhei Nogami, Kiyohiro Yabuuchi, Akira Hasegawa, Takeo Muroga

    Fusion Science and Technology 68 (3) 690-693 2015/10/01

    Publisher: American Nuclear Society

    DOI: 10.13182/FST14-998  

    ISSN: 1536-1055

    eISSN: 1943-7641

  61. Effect of post-weld heat treatment and neutron irradiation on a dissimilar-metal joint between F82H steel and 316L stainless steel

    Haiying Fu, Takuya Nagasaka, Nobuyuki Kometani, Takeo Muroga, Wenhai Guan, Shuhei Nogami, Kiyohiro Yabuuchi, Takuya Iwata, Akira Hasegawa, Masanori Yamazaki, Sho Kano, Yuhki Satoh, Hiroaki Abe, Hiroyasu Tanigawa

    Fusion Engineering and Design 98-99 1968-1972 2015/10

    DOI: 10.1016/j.fusengdes.2015.06.079  

    ISSN: 0920-3796

    eISSN: 1873-7196

  62. Effects of temperature and strain rate on the tensile properties of potassium-doped tungsten

    Kenta Sasaki, Kiyohiro Yabuuchi, Shuhei Nogami, Akira Hasegawa

    Journal of Nuclear Materials 461 357-364 2015/06

    DOI: 10.1016/j.jnucmat.2015.03.015  

    ISSN: 0022-3115

    eISSN: 1873-4820

  63. Effects of Ta and C on irradiation hardening of austenitic stainless Peer-reviewed

    Yasuyuki SAKAI, Yutaka KURIBAYASHI, Kiyohiro YABUUCHI, Akira HASEGAWA, Shuhei NOGAMI, Junya KANEDA, Naoto SHIGENAKA

    Journal of Plasma and Fusion Research SERIES 11 83-88 2015/03/30

  64. Thermo-mechanical analysis of tungsten and its alloys monoblock divertor under heat load conditions relevant to a fusion reactor Peer-reviewed

    Makoto FUKUDA, Shuhei NOGAMI, Akira HASEGAWA, Kiyohiro YABUUCHI, Koichiro EZATO, Satoshi SUZUKI, Hitoshi TAMURA, Takeo MUROGA

    Journal of Plasma and Fusion Research SERIES 11 99-103 2015/03/30

  65. Microstructural development of tungsten and tungsten–rhenium alloys due to neutron irradiation in HFIR

    Makoto Fukuda, Kiyohiro Yabuuchi, Shuhei Nogami, Akira Hasegawa, Teruya Tanaka

    Journal of Nuclear Materials 455 (1-3) 460-463 2014/12

    DOI: 10.1016/j.jnucmat.2014.08.002  

    ISSN: 0022-3115

    eISSN: 1873-4820

  66. Effect of He implantation on fracture behavior and microstructural evolution in F82H

    Kiyohiro Yabuuchi, Kiminori Sato, Shuhei Nogami, Akira Hasegawa, Masami Ando, Hiroyasu Tanigawa

    Journal of Nuclear Materials 455 (1-3) 690-694 2014/12

    DOI: 10.1016/j.jnucmat.2014.09.018  

    ISSN: 0022-3115

    eISSN: 1873-4820

  67. Neutron irradiation effects on tungsten materials

    Akira Hasegawa, Makoto Fukuda, Shuhei Nogami, Kiyohiro Yabuuchi

    Fusion Engineering and Design 89 (7-8) 1568-1572 2014/10

    DOI: 10.1016/j.fusengdes.2014.04.035  

    ISSN: 0920-3796

    eISSN: 1873-7196

  68. Depth-dependent nanoindentation hardness of reduced-activation ferritic steels after MeV Fe-ion irradiation

    Ryuta Kasada, Satoshi Konishi, Kiyohiro Yabuuchi, Shuhei Nogami, Masami Ando, Dai Hamaguchi, Hiroyasu Tanigawa

    Fusion Engineering and Design 89 (7-8) 1637-1641 2014/10

    DOI: 10.1016/j.fusengdes.2014.03.068  

    ISSN: 0920-3796

    eISSN: 1873-7196

  69. Tensile properties of K-doped W–3%Re

    Makoto Fukuda, Shuhei Nogami, Akira Hasegawa, Hiroshi Usami, Kiyohiro Yabuuchi, Takeo Muroga

    Fusion Engineering and Design 89 (7-8) 1033-1036 2014/10

    DOI: 10.1016/j.fusengdes.2014.02.062  

    ISSN: 0920-3796

    eISSN: 1873-7196

  70. A dual ion irradiation study of helium–dpa interactions on cavity evolution in tempered martensitic steels and nanostructured ferritic alloys

    Takuya Yamamoto, Yuan Wu, G. Robert Odette, Kiyohiro Yabuuchi, Sosuke Kondo, Akihiko Kimura

    Journal of Nuclear Materials 449 (1-3) 190-199 2014/06

    DOI: 10.1016/j.jnucmat.2014.01.040  

    ISSN: 0022-3115

    eISSN: 1873-4820

  71. Microstructure development of dispersion-strengthened tungsten due to neutron irradiation

    Makoto Fukuda, Akira Hasegawa, Shuhei Nogami, Kiyohiro Yabuuchi

    Journal of Nuclear Materials 449 (1-3) 213-218 2014/06

    DOI: 10.1016/j.jnucmat.2013.10.012  

    ISSN: 0022-3115

    eISSN: 1873-4820

  72. Evaluation of irradiation hardening of proton irradiated stainless steels by nanoindentation

    Kiyohiro Yabuuchi, Yutaka Kuribayashi, Shuhei Nogami, Ryuta Kasada, Akira Hasegawa

    Journal of Nuclear Materials 446 (1-3) 142-147 2014/03

    DOI: 10.1016/j.jnucmat.2013.12.009  

    ISSN: 0022-3115

    eISSN: 1873-4820

  73. Effects of tool rotation speed on the mechanical properties and microstructure of friction stir welded ODS steel

    Kiyohiro Yabuuchi, Naoto Tsuda, Akihiko Kimura, Yoshiaki Morisada, Hidetoshi Fujii, Hisashi Serizawa, Shuhei Nogami, Akira Hasegawa, Takuya Nagasaka

    Materials Science and Engineering: A 595 291-296 2014/02

    DOI: 10.1016/j.msea.2013.12.022  

    ISSN: 0921-5093

    eISSN: 1873-4936

  74. Neutron Irradiation Effects on Grain-refined W and W-alloys Peer-reviewed

    A. Hasegawa, M. Fukuda, T. Tanno, S. Nogami, K. Yabuuchi, T.Tanaka, T.Muroga

    Proceedings of 25th IAEA Fusion Energy Conference 2014

  75. Effect of Rotation Speed on Microstructure and Hardness of Friction Stir Welded ODS Ferritic Steel

    W.T. Han, N. Tsuda, D.S. Chen, Y. Ha, H. Je, H. Noto, Y. Morisada, H. Serizawa, H. Fujii, K. Yabuuchi, A. Kimura

    Proceedings of the 1st International Joint Symposium on Joining and Welding (IJS-JW2013) 81-85 2013/11

  76. Nanoindentation hardness and its extrapolation to bulk-equivalent hardness of F82H steels after single- and dual-ion beam irradiation

    Y. Takayama, R. Kasada, Y. Sakamoto, K. Yabuuchi, A. Kimura, M. Ando, D. Hamaguchi, H. Tanigawa

    Journal of Nuclear Materials 442 (1-3) S23-S27 2013/11

    DOI: 10.1016/j.jnucmat.2012.12.033  

    ISSN: 0022-3115

    eISSN: 1873-4820

  77. Effect of alloying elements on irradiation hardening behavior and microstructure evolution in BCC Fe

    Kiyohiro Yabuuchi, Ryuta Kasada, Akihiko Kimura

    Journal of Nuclear Materials 442 (1-3) S790-S795 2013/11

    DOI: 10.1016/j.jnucmat.2013.04.035  

    ISSN: 0022-3115

    eISSN: 1873-4820

  78. Effect of Mn addition on one-dimensional migration of dislocation loops in body-centered cubic Fe

    Kiyohiro Yabuuchi, Ryuta Kasada, Akihiko Kimura

    Acta Materialia 61 (17) 6517-6523 2013/10

    DOI: 10.1016/j.actamat.2013.07.029  

    ISSN: 1359-6454

  79. Ion-Irradiation Hardening of Brazed Joints of Tungsten and Oxide Dispersion Strengthened (ODS) Ferritic Steel

    Y. Himei, K. Yabuuchi, R. Kasada, S. Noh, H. Noto, T. Nagasaka, S. Nogami, A. Kimura

    MATERIALS TRANSACTIONS 54 (4) 446-450 2013

    DOI: 10.2320/matertrans.mg201212  

    ISSN: 1345-9678

    eISSN: 1347-5320

  80. Bend Stress Relaxation of Pure Tungsten

    Kenta SASAKI, Shuhei NOGAMI, Makoto FUKUDA, Kiyohiro YABUUCHI, Akira HASEGAWA

    Plasma and Fusion Research 8 1405006-1405006 2013

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.8.1405006  

    ISSN: 1880-6821

    eISSN: 1880-6821

  81. Dose dependence of irradiation hardening of binary ferritic alloys irradiated with Fe3+ ions

    Kiyohiro Yabuuchi, Hiroki Yano, Ryuta Kasada, Hirotatsu Kishimoto, Akihiko Kimura

    Journal of Nuclear Materials 417 (1-3) 988-991 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.204  

    ISSN: 0022-3115

    eISSN: 1873-4820

  82. A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques

    Ryuta Kasada, Yoshiyuki Takayama, Kiyohiro Yabuuchi, Akihiko Kimura

    Fusion Engineering and Design 86 (9-11) 2658-2661 2011/10

    DOI: 10.1016/j.fusengdes.2011.03.073  

    ISSN: 0920-3796

  83. Neutron irradiation hardening and microstructure changes in Fe–Mn binary alloys

    Kiyohiro Yabuuchi, Masashi Saito, Ryuta Kasada, Akihiko Kimura

    Journal of Nuclear Materials 414 (3) 498-502 2011/07

    DOI: 10.1016/j.jnucmat.2011.05.008  

    ISSN: 0022-3115

  84. Neutron Irradiation Hardening of Fe-Based Binary Alloys Peer-reviewed

    Kiyohiro Yabuuchi, Masashi Saito, Ryuta Kasada, Akihiko Kimura

    PRICM 7, PTS 1-3 654-656 2911 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2911  

    ISSN: 0255-5476

  85. Evaluation of Irradiation Hardening of Fe-Ion Irradiated F82H by Nano-Indentation Techniques

    Yoshiyuki Takayama, Ryuta Kasada, Kiyohiro Yabuuchi, Akihiko Kimura, Dai Hamaguchi, Masami Ando, Hiroyasu Tanigawa

    PRICM 7, PTS 1-3 654-656 2915 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2915  

    ISSN: 0255-5476

  86. Relation between martensite morphology and volume change accompanying fcc to bcc martensitic transformation in Fe–Ni–Co alloys

    A. Shibata, H. Yonezawa, K. Yabuuchi, S. Morito, T. Furuhara, T. Maki

    Materials Science and Engineering: A 438-440 241-245 2006/11

    DOI: 10.1016/j.msea.2005.12.044  

    ISSN: 0921-5093

Show all ︎Show first 5

Misc. 35

  1. 複合ビーム材料照射装置DuETを用いた核融合炉材料研究と関連材料研究の展開—Research on Fusion Reactor Materials and Related Materials using the Dual-Beam Facility for Energy Science and Technology DuET

    藪内 聖皓, 近藤 創介, 檜木 達也, 笠田 竜太

    プラズマ・核融合学会誌 = Journal of plasma and fusion research / プラズマ・核融合学会編集委員会 編 97 (7) 403-418 2021/07

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  2. Instructions for Preparing Manuscripts for JSPF Annual Meeting

    LIU Yuchen, 笠田竜太, GAO Zimo, YU Hao, 近藤創介, 藪内聖皓, MOHAMAD Aghamiri, 大野直子, 鵜飼重治, 能登裕之, 菱沼良光, 室賀健夫

    プラズマ・核融合学会年会(Web) 37th 2020

  3. ベリリウム金属間化合物の化学状態分析の解析にはじめて成功

    向井 啓祐, 笠田 竜太, 藪内 聖皓, 小西 哲之, 金 宰煥, 中道 勝

    Isotope News 766 (12) 11-14 2019/12

  4. Development of high ductile ODS ferritic steel for advanced energy system

    N.Y. Iwata, Y. Morizono, S. Suzuki, K. Yabuuchi, A. Kimura

    Proceedings of the 10th International Symposium of Advanced Energy Science, Kyoto, Japan 215 2019/10

  5. Iron-ion irradiation effects on microstructure of yttrium oxide coating fabricated by magnetron sputtering

    Kazuki Nakamura, Hikari Fujita, Jan Engels, Masayuki Tokitani, Yoshimitsu Hishinuma, Kiyohiro Yabuuchi, Sosuke Kondo, Sho Kano, Takayuki Terai, Takumi Chikada

    Fusion Engineering and Design 146 2031-2035 2019/09/01

    DOI: 10.1016/j.fusengdes.2019.03.093  

    ISSN: 0920-3796

  6. 粒子線照射された3C-SiCの高温高圧水腐食

    近藤創介, 笠田竜太, YU Hao, 前田有輝, 深見一弘, 藪内聖皓, 檜木達也

    日本セラミックス協会年会講演予稿集(CD-ROM) 2019 2019

  7. マグネトロンスパッタリング法で作製した酸化イットリウム被覆の微細構造および水素同位体透過挙動に対する重イオン照射効果

    中村和貴, 藤田光, ENGELS Jan, 藪内聖皓, 近藤創介, 叶野翔, 寺井隆幸, 近田拓未

    日本原子力学会秋の大会予稿集(CD-ROM) 2018 ROMBUNNO.2N13 2018/08/20

  8. マグネトロンスパッタリング法で作製した酸化イットリウム被覆中の重水素透過挙動とその鉄イオン照射効果

    近田拓未, 近田拓未, ENGELS Jan, HOUBEN Anne, 堀越清良, 望月惇平, 藤田光, 松永萌暉, 近藤創介, 藪内聖皓, 大矢恭久, 大矢恭久

    日本原子力学会春の年会予稿集(CD-ROM) 2017 ROMBUNNO.1B09 2017/03/09

  9. 事故時高温条件での燃料健全性確保のためのODSフェライト鋼燃料被覆管の研究開発(3)(8)α/α’相分離影響評価(まとめ)

    木村晃彦, 藪内聖皓, 鳥丸忠彦, 鵜飼重治, 大野直子, 皆藤威二, 林重成

    日本原子力学会春の年会予稿集(CD-ROM) 2017 2017

  10. 事故時高温条件での燃料健全性確保のためのODSフェライト鋼燃料被覆管の研究開発(3)(7)熱時効影響評価(熱時効硬化・脆化)

    藪内聖皓, 木村晃彦, 鳥丸忠彦, 鵜飼重治, 大野直子, 皆藤威二, 林重成

    日本原子力学会春の年会予稿集(CD-ROM) 2017 2017

  11. 事故耐性型ODS鋼燃料被覆管の接合技術開発(2)

    湯澤翔, 藪内聖皓, 木村晃彦, 坂本寛, 平井睦, 山下真一郎

    日本金属学会講演概要(CD-ROM) 161st 2017

    ISSN: 2433-3093

  12. Industry Support Program by Dual-beam Materials Irradiation Accelerator

    木村晃彦, 檜木達也, 笠田竜太, 藪内聖皓, 松井秀樹, 近藤創介

    加速器 12 (4) 217‐221-221 2016/01/31

    Publisher: Particle Accelerator Society of Japan

    DOI: 10.50868/pasj.12.4_217  

    ISSN: 1349-3833

    eISSN: 2436-1488

    More details Close

    Dual-beam irradiation facility for Energy science and Technology (DuET) has been used to support nuclear industry researches as well as those of non-nuclear field. Both the in-situ and post-irradiation experimental techniques, which are critical to understand radiation damage mechanisms such as irradiation creep, irradiation hardening evaluation by nano-indentation method and fabrication procedure of TEM thin foiles, are introduced. Besides radiation induced lattice defect formation, an example of surface modification technology using ion-accelerators is also introduced.

  13. 長寿命超ウラン元素を燃焼可能な軽水炉RBWRの開発(8)制御棒用高照射環境下耐食材料の開発

    石嵜貴大, 丸野祐策, 藪内聖皓, 近藤創介, 木村晃彦, 松井秀樹

    日本原子力学会秋の大会予稿集(CD-ROM) 2015 ROMBUNNO.A07 2015/08/21

  14. 原子炉燃料被覆管の安全設計基準に資する環境劣化評価手法に関する研究(3)材料特性の環境劣化影響の評価

    叶野翔, 楊会龍, 艶芬李, 松川義孝, 佐藤祐樹, 藪内聖皓, 長谷川晃, 阿部弘亨, 村瀬義治, 山本徳和

    日本原子力学会春の年会予稿集(CD-ROM) 2015 ROMBUNNO.C22 2015/03/05

  15. 原子炉燃料被覆管の安全設計基準に資する環境劣化手法に関する研究開発(5)高中エネルギーイオン照射試験法開発

    藪内聖皓, 野上修平, 長谷川晃, 叶野翔, LI Feng, 大場彰, YANG Huilong, 阿部弘亨, 村上健太, 岩井岳夫, 村瀬義治

    日本原子力学会春の年会予稿集(CD-ROM) 2014 ROMBUNNO.F31 2014/03/10

  16. 4.2 Joining and Coating System Integrity(4. Irradiation Synergism,Japan-US Joint Research Project TITAN)

    KIMURA Akihiko, HASHIMOTO Naoyuki, NOH Sanghoon, YABUUCHI Kiyohiro, OHNUKI Somei

    Journal of plasma and fusion research 89 (11) 731-736 2013/11/25

    Publisher: 社団法人プラズマ・核融合学会

    ISSN: 0918-7928

    More details Close

    ブランケット製作における枢要な課題である構造材料の接合・被覆技術開発および接合部の健全性に及ぼす中性子照射影響を調べ,材料システム統合化を行った.開発が困難とされていたODS鋼の接合法として,固相拡散接合(SSDB)および摩擦撹拌接合(FSW)法が適していることや電子ビーム(EB)溶接したF82H鋼ジョイントの照射後引張特性が母材と同等であることが判明した.また,十分な強度をもつW/ODS鋼ジョイント製作の可能性を示した.

  17. 鉄クロム合金のナノインデンテーション硬さ‐ビッカース硬さ相関則とイオン照射材への適用 Peer-reviewed

    笠田竜太, 坂本雄太, 高山嘉幸, 藪内聖皓, 木村晃彦, 佐藤紘一

    日本金属学会2012年秋期大会,愛媛大学,2012.9.17-19 2012

  18. Application of Nano-Indentation Technique to Investigate Irradiation Hardening of Ion-Irradiated Fusion Reactor Materials Peer-reviewed

    R. Kasada, Y. Takayama, Y. Sakamoto, Y. Himei, K. Nakagawa, K. Yabuuchi, A. Kimura

    15th International Conference on Fusion Reactor Materials (ICFRM-15),Hotel Charleston Mariotto, Charleston, SC, USA,2011.10.16-22 2011

  19. Interfacial Shear Strength of W-Coated ODS Steel and Ion Irradiation Effects of Tungsten Peer-reviewed

    Y. Himei, S.H. Noh, R. Kasada, A. Kimura, K. Yabuuchi, T. Nagasaka, S. Nogami

    15th International Conference on Fusion Reactor Materials (ICFRM-15),Hotel Charleston Mariotto, Charleston, SC, USA ,2011.10.16-22 2011

  20. Effects of Mn on the microstructural evolution of bcc Fe irradiated by neutrons and Fe3+ ions, Peer-reviewed

    K. Yabuuchi, R. Kasada, A. Kimura

    Workshop on Ion Implantationas a Neutron Irradiation Analogue,Oxford University, Oxford, UK,2011.9.26-28 2011

  21. Development and Integrity Assessment of Joints and Coatings of Advanced First-wall Structural Materials Peer-reviewed

    A. Kimura, N. Hashimoto, S.H. Noh, K. Yabuuchi, H. Noto, R. Kasada, S. Nogami, H. Kurishita, T. Nagasaka, T. Yamamoto, M. Sokolov

    The 2011 International Symposium on Advanced Engineering,Pukyong National University, Busan, Korea,2011.11.10 2011

  22. Nano indentation hardness and its extrapolation to Vickers hardness of F82H steels after single- and dual-ion beam irradiation, Peer-reviewed

    Y. Takayama, Y. Sakamoto, R. Kasada, K. Yabuuchi, A. Kimura, M. Ando, D. Hamaguchi, H. Tanigawa

    15th International Conference on Fusion Reactor Materials (ICFRM-15),Hotel Charlest on Mariotto, Charleston, SC, USA,2011.10.16-22 2011

  23. イオン照射したFe-Mn合金における転位ループの照射後焼鈍回復挙動 Peer-reviewed

    藪内聖皓, 笠田竜太, 木村晃彦

    日本金属学会2011年秋期(第149回)講演大会,沖縄コンベンションセンター,2011.11.7-9 2011

  24. W-ODS鋼接合材の界面せん断応力とWのイオン照射効果 Peer-reviewed

    姫井善正, Noh Sanghoon, 笠田竜太, 木村晃彦, 薮内聖皓, 長坂琢也, 野上修平

    日本金属学会2011年秋期(第149回)講演大会,沖縄コンベンションセンター,2011.11.7-9 2011

  25. 先進核融合炉ブランケット用ODS 鋼の接合・被覆技術開発 Peer-reviewed

    盧相熏, 藪内聖皓, 大野直子, 岩田憲幸, 笠田竜太, 長坂琢也, 檜木達也, 木村晃彦, 橋本直幸, 大貫惣明, 鵜飼重治, M. Sokolov, T. Yamamoto

    第8回核融合エネルギー連合講演会 新たなエネルギー革命を起こす科学技術“核融合” 2010/06/10

  26. Nano-indentation Hardness of Ion-irradiated Ferritic Alloys for Advanced Nuclear Systems Peer-reviewed

    R. Kasada, Y. Takayama, K. Yabuuchi, A. Kimura, D. Hamaguchi, M. Ando, H. Tanigawa

    The Tenth Japan-China Symposium (JCS-10) on Materials for Advanced Energy Systems and Fission & Fusion Engineering, Obaku Plaza, Kyoto University, 2010.10.19-22 2010

  27. イオン照射法による低放射化フェライト鋼の照射硬化評価技術の高度化に関する研究 Peer-reviewed

    高山嘉幸, 笠田竜太, 藪内聖皓, 木村晃彦, 浜口大, 安藤正巳, 谷川博康

    第8回核融合エネルギー連合講演会,高山市民文化会館,2010.6.10-11 2010

  28. イオン照射した鉄二元系合金の照射硬化挙動 Peer-reviewed

    藪内聖皓, 笠田竜太, 木村晃彦

    日本金属学会2010年秋期(第147回)大会,北海道大学,2010.9.25-27 2010

  29. イオン照射した鉄鋼材料における超微小硬さ Peer-reviewed

    笠田竜太, 高山嘉幸, 藪内聖皓, 木村晃彦

    「原子炉圧力容器鋼照射脆化機構研究の最近の進展」ワークショップ,東北大学金属材料研究所,2010.7.30 2010

  30. 鉄基合金を用いた照射硬化機構の基礎的研究 Peer-reviewed

    藪内聖皓, 笠田竜太, 木村晃彦

    第8回核融合エネルギー連合講演会,高山市民文化会館,2010.6.10-11 2010

  31. イオン照射したFe-Mn二元系合金の照射硬化挙動 Peer-reviewed

    藪内聖皓, 笠田竜太, 木村晃彦

    日本金属学会2009年秋期(第145回)大会,京都大学,2009.9.15-17 2009

  32. Irradiation Hardening Behavior of RPV Steel and Fe-Mn Alloys after Neutron and Fe-ion Irradiation Peer-reviewed

    K Yabuuchi, R Kasada, H Yano, H Kishimoto, A Kimura, Y Nagai, M Hasegawa

    ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle, Denver, USA, 2008.6.24-26 2008

  33. ,Feイオン照射したFe-Mn合金の照射硬化挙動 Peer-reviewed

    矢野弘樹, 藪内聖皓, 岸本弘立, 笠田竜太, 木村晃彦

    日本金属学会2007年春期大会,千葉工業大学津田沼キャンパス,2007.3.27-29 2007

  34. 原子炉圧力容器鋼モデル合金の照射硬化挙動に及ぼすマンガン影響に関する研究 Peer-reviewed

    藪内聖皓, 笠田竜太, 木村晃彦

    第2回(平成18年度)日本原子力学会関西支部「若手研究者による研究発表会」,大阪大学,2006.10.26 2006

  35. 圧力容器鋼の照射脆化評価における Mn 影響のインパクト Peer-reviewed

    木村晃彦, 笠田竜太, 薮内聖皓, 矢野弘樹

    日本金属学会2006年秋期(第139回)大会,新潟大学,2006.9.16-18 2006

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Presentations 46

  1. Energetic consideration of shape change from a stacking fault tetrahedron into a void in FeCrNi alloy

    Kiyohiro Yabuuchi, Yotaro Kakuda

    NuMat2024 2024/10/16

  2. CVDによるSiC保護被膜のプロセスインフォマティクス Invited

    藪内聖皓, 且井宏和, 下田一哉, 江原真司, 近藤創介

    日本MRS年次大会

  3. Obstacle strength factor of faceted voids in bcc Fe

    Kiyohiro Yabuuchi, Tomoaki Suzudo

    ICFRM20 2021/10

  4. Investigation of the reaction process between an edge dislocation and a faceted void with MD simulation

    Kiyohiro Yabuuchi, Tomoaki Suzudo

    PRICM9 2016/08/04

  5. 耐SCC材料の開発 (3)SUS304系ステンレス鋼の照射硬化に及ぼすTaの影響

    日本原子力学会2013春の年会 2013

  6. Relationship between Grain Boundary Character and Crack Initiation of He irradiated Fe-15Cr-20Ni Ternary Alloy

    TMS2013 142nd Annual Meeting & Exhibition 2013

  7. 転位ループによる転位デコレーションの形成メカニズムに関する研究

    金属学会 2013年秋期講演大会 2013

  8. 耐SCC材料の開発 (3)SUS304系ステンレス鋼の照射硬化に及ぼすTaの影響

    日本原子力学会2013春の年会 2013

  9. Relationship between Grain Boundary Character and Crack Initiation of He irradiated Fe-15Cr-20Ni Ternary Alloy

    TMS2013 142nd Annual Meeting & Exhibition 2013

  10. 転位ループによる転位デコレーションの形成メカニズムに関する研究

    金属学会 2013年秋期講演大会 2013

  11. Evaluation of mechanical properties of friction stir welded ODS ferritic steel

    NuMat2012 2012

  12. Mn effect on 1D motion of dislocation loops in BCC Fe.

    NuMat2012 2012

  13. Evaluation of mechanical properties of friction stir welded ODS ferritic steel

    NuMat2012 2012

  14. Mn effect on 1D motion of dislocation loops in BCC Fe.

    NuMat2012 2012

  15. イオン照射した鉄二元系合金の微細組織発達

    日本金属学会2011年春期(第148回)大会 2011

  16. Mn Effect on irradiation hardening and microstructural evolution in BCC Fe

    ICFRM15 2011

  17. イオン照射したFe-Mn合金における転位ループの照射後焼鈍回復挙動

    日本金属学会2011年秋期(第149回)大会 2011

  18. Mn Effect on irradiation hardening and microstructural evolution in BCC Fe

    Workshop on Ion Implantation as Neutron analogue 2011

  19. イオン照射した鉄二元系合金の微細組織発達

    日本金属学会2011年春期(第148回)大会 2011

  20. Mn Effect on irradiation hardening and microstructural evolution in BCC Fe

    ICFRM15 2011

  21. イオン照射したFe-Mn合金における転位ループの照射後焼鈍回復挙動

    日本金属学会2011年秋期(第149回)大会 2011

  22. Mn Effect on irradiation hardening and microstructural evolution in BCC Fe

    Workshop on Ion Implantation as Neutron analogue 2011

  23. イオン照射したFe-Mn二元系合金の照射硬化回復挙動

    日本金属学会秋季(第146回)大会 2010

  24. 鉄基合金を用いた照射硬化機構の基礎的研究

    第8回核融合連合講演会 2010

  25. Neutron Irradiation Hardening of Fe-based Binary Alloys

    PRICM7 2010

  26. イオン照射した鉄二元系合金の照射硬化挙動

    日本金属学会2010年秋期(第147回)大会 2010

  27. Effects of solute atoms on the microstructural evolution and irradiation hardening in ion-irradiated Fe binary alloys

    NuMat 2010 2010

  28. イオン照射したFe-Mn二元系合金の照射硬化回復挙動

    日本金属学会秋季(第146回)大会 2010

  29. 鉄基合金を用いた照射硬化機構の基礎的研究

    第8回核融合連合講演会 2010

  30. Neutron Irradiation Hardening of Fe-based Binary Alloys

    PRICM7 2010

  31. イオン照射した鉄二元系合金の照射硬化挙動

    日本金属学会2010年秋期(第147回)大会 2010

  32. Effects of solute atoms on the microstructural evolution and irradiation hardening in ion-irradiated Fe binary alloys

    NuMat 2010 2010

  33. イオン照射したFe-Mn二元系合金の照射硬化挙動

    日本金属学会秋季(第145回)大会 2009

  34. Dose dependence of irradiation hardening of binary ferritic alloys irradiated with Fe3+ ions

    ICFRM14 2009

  35. The Mn Effects -Are the defects unstable?-

    IGRDM15 2009

  36. イオン照射したFe-Mn二元系合金の照射硬化挙動

    日本金属学会秋季(第145回)大会 2009

  37. Dose dependence of irradiation hardening of binary ferritic alloys irradiated with Fe3+ ions

    ICFRM14 2009

  38. The Mn Effects -Are the defects unstable?-

    IGRDM15 2009

  39. Fe-Mn系モデル合金の照射硬化挙動

    日本金属学会2006年春期(第138回)大会 2006

  40. ffects of Mn Contents on Irradiation Hardening of Fe-Mn Model Alloys

    The 23rd symposium on Effects of Radiation on Materials 2006

  41. Fe-Mn系モデル合金の照射硬化挙動

    日本原子力学会2006年秋の大会 2006

  42. Fe-Mn系モデル合金の照射硬化挙動(2)

    日本金属学会2006年秋期(第139回)大会 2006

  43. Fe-Mn系モデル合金の照射硬化挙動

    日本金属学会2006年春期(第138回)大会 2006

  44. ffects of Mn Contents on Irradiation Hardening of Fe-Mn Model Alloys

    The 23rd symposium on Effects of Radiation on Materials 2006

  45. Fe-Mn系モデル合金の照射硬化挙動

    日本原子力学会2006年秋の大会 2006

  46. Fe-Mn系モデル合金の照射硬化挙動(2)

    日本金属学会2006年秋期(第139回)大会 2006

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Research Projects 17

  1. 核融合炉で使用後10年以内に再利用可能な低放射化バナジウム合金の試作開発

    長坂 琢也, 福元 謙一, 田中 照也, 外山 健, 小林 真, 矢嶋 美幸, 山内 有二, 申 晶潔, 片山 一成, 藪内 聖皓

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 基盤研究(A)

    Institution: 核融合科学研究所

    2020/04/01 - 2025/03/31

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    バナジウム(V)の帯溶融精製においては、10年後の放射能に最も大きく影響する不純物Coの偏析係数を実験と数値解析で評価したところ、V中のそれは0.5~0.6であり、例えばFe中のCo(偏析係数0.9程度)より小さいために、大きな除去効率が期待できることが明らかとなった。現在の候補合金NIFS-HEAT-2のCo濃度0.7 mass ppmに比較して、本研究では0.01 mass ppmまで1/70の低減に成功したのはこの小さな偏析係数が要因となっている。これにより、工業的に応用可能な比較的簡易的な精製でも、核融合炉で使用後10年以下での再利用に必要なCo濃度目標値0.1 mass ppm以下まで低減できる見込みが得られた。 強度及び加速器イオン照射特性にもとづいて候補組成の絞込みを実施し、体積の大きな衝撃試験片を作製して中性子照射に供すべき組成としてV-4mass%Cr-4mass%Ti、V-6Cr-3Ti、V-8Cr-2Ti、V-10Cr-1Ti、V-12Cr-0.5Tiの5種類を選定し150 gの合金を作製した。 ベルギー材料試験炉BR-2での中性子照射計画の検討を行い、サブキャプセルの設計と装荷試料マトリクスを策定した。照射温度500℃においてV合金の酸化を避けるため、ステンレス製照射サブキャプセルに真空封入することとした。このとき、サブキャプセルの外側、すなわち格納されるキャプセル内にはHeガスが充填されるため、高温ではその圧力により座屈の可能性が生じる。座屈応力の解析と工作精度に関わる安全係数の検討により、サブキャプセルの壁厚を0.8 mmに設定した。 加速器イオン照射実験では、Ti濃度1 mass%の合金は0.5 dpa照射での照射硬化が他の合金より大きいことが示唆されていたが、この傾向は10 dpaにおいても認められた。詳細なメカニズムについては解析、検討中である。

  2. Exploring the missing link in irradiation embrittlement using ultra-small testing technologies

    KASADA RYUTA

    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: Tohoku University

    2019/04/01 - 2022/03/31

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    This study succeeded in directly evaluating deformation and fracture phenomena of nuclear fission and fusion materials at microscale by using ultra-small testing technologies such as nanoindentation and micropillar compression tests. Microstructural factors and irradiation effects on the scale-factor of deformation and fracture behavior of oxide dispersion strengthened alloys, reactor pressure vessel steels, and tungsten coating interfaces were clarified. In particular, the mechanical properties of precipitates and interfaces, which are the missing links between microstructural changes and macroscopic deformation and fracture phenomena that are considered to be factors of irradiation embrittlement, can be directly evaluated, providing a method to integrate irradiation effects on microstructural factors that have not been considered in irradiation embrittlement models.

  3. Effects of domain wall on diffusion of defects

    Yabuuchi Kiyohiro

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Early-Career Scientists

    Institution: Kyoto University

    2019/04/01 - 2021/03/31

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    Irradiation embrittlement, the phenomenon which the property of components of fusion reactors was degraded by neutrons generated in the fusion plasma, is one of the most important issue of safety of fusion reactor. In this study, we focused on the effect of magnetic domain on the irradiation effect. Pure Fe was used for the materials and the ion irradiation experiments was performed using the ion accelerator DuET in Institute of Advanced Energy, Kyoto University. Experimental and computational study revealed the relationship between magnetic effect and microstructure evolution.

  4. Modeling tolerance to irradiation embrittlement of reduced activation ODS steels by quantitative specification of nano-mezo structures

    Kimura Akihiko

    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: Kyoto University

    2018/04/01 - 2021/03/31

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    A quantitative evaluation method of radiation tolerance of ODS steels was developed on the bases of materials science of microstructure. Irradiation hardening and microstructure evolution in ion-irradiated three ODS steels were investigated by means of nano-indentation tests and high resolution transmission electron microscopy (HRTEM). The hardness test results indicated that the hardening depended on material, namely, the oxide particles of which the chemical compositions, size and number density were different. HRTEM revealed that there was a relationship between the amount of hardening and the interface structure between oxide particle and matrix. Moreover, it was shown that the amount of irradiation hardening can be correlated with the unit size of Moire pattern at the interface of oxide particle and matrix.Thus, the radiation tolerance of ODS steels can be quantitatively evaluated from TEM observation of oxides in the matrix of ODS steels.

  5. 強度因子の異なる欠陥が混在する組織における材料強度評価モデルの構築 Competitive

    藪内 聖皓

    System: 科学研究費補助金

    2016/04 - 2019/03

  6. A Challenge to Development of Functionally-graded Long-life Divertor based on Degradation Behavior Caused by Thermal Fatigue of Tungsten

    Nogami Shuhei

    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: Tohoku University

    2014/04/01 - 2018/03/31

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    The objective of this research is development of functionally-graded tungsten (W) for divertor using a void dispersion strengthened W (VDSW) and a nano structure controlled W (NSCW). Based on the fundamental mechanical properties, recrystallization behavior, fatigue properties, and resistance to the beam bombardment, development of the VDSW and NSCW was carried out and the excellent performance was shown by these materials. Development of a new testing machine for evaluating the fatigue properties was also carried out and the available data of these materials were obtained. In contrast, the evaluation of resistance to helium implantation was carried out under the only limited evaluation conditions. This is one of the issues to be improved by future works. However, the development of fabrication technology of reasonable joints using VDSW and NSCW was all but almost over. Therefore, the objective of this research is considered to be basically achieved.

  7. 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

    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.

  8. Study on mechanism of grain boundary embrittlement of austenitic stainless steel after irradiation using in-situ monitoring system of grain boundary separation

    HASEGAWA Akira, YABUUCHI Kiyohiro

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Challenging Exploratory Research

    Institution: Tohoku University

    2012/04/01 - 2014/03/31

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    Helium embrittlement of austenitic stainless steel by tensile mode was investigated though grain boundary observation of solution-annealed and He-implanted Fe-15Cr-20Ni at high temperature. The following results were obtained. Grain boundary separation appeared during the elastic deformation area at 923 and 1023K. The separated grain boundaries were observed only after yielding tested at 823K, and these were not observed below 723K. These separated grain boundaries were random or higher grain boundaries and their direction was near perpendicularly to the stress direction. With increasing plastic strain, separated grain boundaries of lower sigma boundaries were observed. With increasing the applied strain, separated grain boundaries were linked and formed grain boundary cracks and before the specimen rupture. In-situ observation system for surface crack formation during tensile test was designed and manufactured, and the analysis of deformation mode is under investigated.

  9. オーステナイト鋼中における空孔集合体のエネルギーハイラキーに及ぼす因子の解明 Competitive

    System: その他の研究制度

    2013 - 2014

  10. Factor affecting the energy hierarchy of vacancy clusters in austenitic steels Competitive

    System: The Other Research Programs

    2013 - 2014

  11. Heバブルによる照射硬化メカニズムの解明 Competitive

    System: その他の研究制度

    2013 - 2013

  12. 低放射化フェライト鋼の機械特性に及ぼすヘリウムの影響評価 Competitive

    System: その他の研究制度

    2013 - 2013

  13. Mechanisms of irradiation hardening due to He bubbles Competitive

    System: The Other Research Programs

    2013 - 2013

  14. Effect of He implantation on the mechanical property of reduced activation ferritic/martensitic steels Competitive

    System: The Other Research Programs

    2013 - 2013

  15. 空孔集合体の転位に対する障壁メカニズムの解明 Competitive

    System: 科学研究費補助金

    2012 - 2013

  16. Barrier mechanisms of a vacancy cluster for a dislocation Competitive

    System: Grant-in-Aid for Scientific Research

    2012 - 2013

  17. 高経年化原子炉圧力容器鋼の照射脆化に及ぼすMn影響の解明

    藪内 聖皓

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 特別研究員奨励費

    Institution: 京都大学

    2009 - 2011

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    前年度までに、Fe-Mn合金において顕著な照射硬化が発現することを見出し、その顕著な照射硬化が微細な転位ループが高密度に分散されていることが原因であることを明らかにしている。本年度はその微細かつ高密度な転位ループの形成メカニズムについて詳細に調べた。Pure-FeおよびFe-Mnモデル合金を作製・加工し、京都大学のイオン加速器においてFeイオンを照射した。照射された各試料について硬さ試験を実施するとともに、その微細組織観察をTEM、FETEMを用いて行った。高密度の転位ループの形成メカニズムについて、転位ループの一次元拡散運動が大きく影響を及ぼしていると考え、昇温ホルダーを用いて、TEM内で温度を上げて時効実験を実施し、転位ループの一次元運動について観察した。Pure-Fe中では、転位ループは350℃以上において容易に一次元拡散運動をしたが、Fe-1.4Mn合金中では、550℃まで転位ループの一次元拡散運動は確認されなかった。このことから、Fe-Mn合金中では、Pure-Feに比べ、転位ループの一次元拡散運動が抑制されることが明らかとなり、Mnが転位ループの拡散運動に影響を及ぼしていることが、高密度の転位ループ形成の一因であることを明らかとした。また、大阪大学超高圧電子顕微鏡センターの有する、超高圧電子顕微鏡を利用し、格子欠陥とMnとの相互作用についても実験を実施した。本成果は、国際会議(2回)、国内会議(3回)にて発表した。

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