Details of the Researcher

PHOTO

Ryuta Kasada
Section
Institute for Materials Research
Job title
Professor
Degree
  • Dr. of Energy Science (Kyoto University)

  • M.S. of Engineering (Tohoku University)

Research History 11

  • 2025 - Present
    Tohoku University Institute for Materials Research International Research Center for Nuclear Materials Science Deputy head

  • 2024/04 - Present
    Tohoku University Special Advisor (Public Relations)

  • 2017/10 - Present
    Tohoku University Institute for Materials Research Professor

  • 2025/06 - 2026/03
    Keio University

  • 2023/04 - 2025/03
    National Institute for Fusion Science

  • 2019/04 - 2020/03
    National Institutes for Quantum and Radiological Science and Technology

  • 2018/04 - 2019/03
    Kyoto University Institute of Advanced Energy

  • 2017/11 - 2018/03
    Kyoto University

  • 2011/12 - 2017/09
    Kyoto University Institute of Advanced Energy Associate Professor

  • 2007/04 - 2011/11
    Kyoto University Institute of Advanced Energy Assistant Professor

  • 2001/04 - 2007/03
    Kyoto University Institute of Advanced Energy Research Associate

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Education 3

  • Kyoto University Graduate School of Energy Science Department of Energy Conversion Science

    1998/04 - 2001/03

  • Tohoku University Graduate School of Engineering Department of Quantum Science and Energy Engineering

    1996/04 - 1998/03

  • Tohoku University Faculty of Engineering

    1992/04 - 1996/03

Committee Memberships 24

  • 文部科学省科学技術・学術審議会 研究計画・評価分科会 核融合科学技術委員会 原型炉開発総合戦略タスクフォース 専門委員(主査)

    2021/07 - 2023/03

  • 原子力規制委員会 原子炉圧力容器に対する供用期間中の破壊靱性の確認方法等の技術評価に関する検討チーム

    2019/07 - 2021/03

  • 文部科学省科学技術・学術審議会 研究計画・評価分科会 核融合科学技術委員会 原型炉開発総合戦略タスクフォース 専門委員(主査代理)

    2015/06 - 2021/03

  • 原子力規制委員会原子力規制庁 原子炉構造材の監視試験方法の技術評価に関する検討チーム 外部専門家

    2015/01 - 2015/06

  • 国立研究開発法人科学技術振興機構 創発的研究支援事業アドバイザー (創発AD)

    2023/10 - 2027/09

  • 日本材料試験技術協会 理事

    2025/04 - 2027/04

  • 文部科学省国立研究開発法人審議会第6期量子科学技術研究開発機構部会 臨時委員

    2025/04 - 2027/04

  • 新潟県 新潟県 原子力発電所の安全管理に関する技術委員会 委員

    2025/04 - 2027/03

  • 日本学術会議 日本学術会議小委員会委員

    2025/05 - 2026/09

  • 日本学術会議 総合工学委員会 エネルギーと科学技術に関する分科会 フュージョンエネルギー小委員会委員

    2025/05 - 2026/09

  • 一般社団法人 日本原子力学会 部会等運営委員会 委員

    - 2026/09

  • 日本原子力学会 「核融合炉の潜在 リスクとその評価手法」研究専門委員会委員

    - 2026/05

  • 国立研究開発法人 日本原子力研究開発機構 大洗原子力工学研究所 燃料材料開発部 燃料・材料技術専門委員会 委員

    2025/09 - 2026/03

  • 大学共同利用機関法人 自然科学研究機構 核融合科学研究所 アウトリーチヘッドクォーター 委員

    2025/05 - 2026/03

  • 日本原子力学会材料部会 副部会長

    2025/04 - 2026/03

  • 国立研究開発法人日本原子力研究開発機構 原子力基礎工学研究・評価委員会 委員

    2025/03 - 2026/03

  • Organization committee of 22th International Conferece on Fusion Reactor Materials Publication committee chair

    2024/05 - 2026/03

  • 国立研究開発法人 量子科学技術研究開発機構 六ヶ所フュージョンエネルギー研究所 核融合炉工学研究委員会 委員

    - 2026/03

  • 国立研究開発法人 量子科学技術研究開発機構 六ヶ所フュージョンエネルギー研究所 原型炉設計合同特別チーム メン バー

    - 2026/03

  • 国立研究開発法人量子科学技術研究開発機構 ITER・BA技術推進委員会 委員

    - 2026/03

  • 京都大学複合原子力科学研究所 実験装置検討委員会委員

    - 2026/03

  • 大学共同利用機関法人 自然科学研究機構 核融合科学研究所 核融合科学研究所 運営会議 人材育成・アウトリーチ委員会 委員

    - 2025/04

  • 文部科学省 科学技術・学術政策研究所 科学技術動向センター 専門調査員

    2014/04 - 2016/03

  • 核融合原型炉開発のための技術基盤構築の中核的役割を担うチーム メンバー

    2013/06 - 2015/03

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Professional Memberships 4

  • THE MATERIAL TESTING RESEARCH ASSOCIATION OF JAPAN

  • The Japan Society of Plasma Science and Nuclear Fusion Research

  • ATOMIC ENERGY SOCIETY OF JAPAN

  • THE JAPAN INSTITUTE OF METALS AND MATERIALS

Research Interests 5

  • mechanical alloying

  • nanoindentation

  • Fusion reactor engineering

  • Fusion reactor materials

  • Nuclear Materials

Research Areas 3

  • Nanotechnology/Materials / Material fabrication and microstructure control /

  • Energy / Nuclear engineering / Nuclear Materials

  • Energy / Nuclear fusion / Fusion reactor materials

Awards 6

  1. 第73回論文賞材料プロセシング部門

    2026/03 日本金属学会 The Role of Y2O3/Hf Co-Doping on the Microstructure and Tensile Properties of Alumina-Forming Co-Cr-Al-Ni ODS Superalloy”, Materials Transactions Vol.65 No.8

  2. 吉川允二核融合エネルギー奨励賞

    2011/12 核融合エネルギーフォーラム

  3. 第1回日本原子力学会材料部会 奨励賞

    2009/09 日本原子力学会材料部会

  4. 第2回日本原子力学会核融合炉工学部会 奨励賞

    2005/09 日本原子力学会核融合炉工学部会

  5. 第5回核融合エネルギー連合講演会 優秀賞

    2004/06 第5回核融合エネルギー連合講演会

  6. 第3回核融合エネルギー連合講演会 優秀賞

    2000/06 第3回核融合エネルギー連合講演会

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Papers 301

  1. Suppression of irradiation hardening in tungsten-coated ferritic steel for fusion reactor blanket applications Peer-reviewed

    Kotaro Seki, Kenta Yoshida, Hotaka Miyata, Akira Hasegawa, Sosuke Kondo, Hao Yu, Yasuyuki Ogino, Kazuyuki Hokamoto, Shigeru Tanaka, Takaaki Koyanagi, Ryuta Kasada

    Journal of Nuclear Materials 607 155657-155657 2025/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.jnucmat.2025.155657  

    ISSN: 0022-3115

  2. Multiscale observation of nano-oxide particles in oxide-dispersion-strengthened Cu alloys Peer-reviewed

    Toshiki Saito, Hao Yu, Zimo Gao, Koji Inoue, Sosuke Kondo, Ryuta Kasada, Yasuyoshi Nagai, Yojiro Oba, Kosuke Hiroi

    Journal of Alloys and Compounds 983 2024/05/05

    DOI: 10.1016/j.jallcom.2024.173852  

    ISSN: 0925-8388

  3. Size dependence of micro-scale mechanical properties on heavy-ion irradiated tempered-martensitic steel evaluated through nanoindentation and micropillar compression tests Peer-reviewed

    Diancheng Geng, Hao Yu, Masami Ando, Hiroyasu Tanigawa, Hironori Kurotaki, Takashi Nozawa, Sosuke Kondo, Ryuta Kasada

    Journal of Nuclear Materials 593 2024/05

    DOI: 10.1016/j.jnucmat.2024.155013  

    ISSN: 0022-3115

  4. Effects of Cr and Si addition on the high-temperature oxidation resistance in high-Mn alumina-forming oxide dispersion strengthened austenitic steels Peer-reviewed

    Diancheng Geng, Hao Yu, Xinwei Yuan, Sosuke Kondo, Junichi Miyazawa, Ryuta Kasada

    Nuclear Materials and Energy 38 2024/03

    DOI: 10.1016/j.nme.2023.101572  

    eISSN: 2352-1791

  5. プロジェクトレビュー 総説 プラズマ・核融合サイエンスチャート3 .歴史と広がり3. History and Diversity 3.5 構造材料・プラズマ対向材料

    笠田竜太

    プラズマ・核融合学会誌 100 (1) 28-34 2024/01

  6. Mechanical properties of the W coating and interface of vacuum-plasma-sprayed W–ferritic steel joints under shear and bending loads Peer-reviewed

    Wu, X., Kondo, S., Yu, H., Nagasaka, T., Kasada, R.

    Surface and Coatings Technology 462 2023

    DOI: 10.1016/j.surfcoat.2023.129468  

    ISSN: 0257-8972

  7. Characterization and corrosion behavior of Al-added high Mn ODS austenitic steels in oxygen-saturated lead-bismuth eutectic Peer-reviewed

    Haoran Wang, Hao Yu, Jiarui Liu, Sosuke Kondo, Nariaki Okubo, Ryuta Kasada

    CORROSION SCIENCE 209 2022/12

    DOI: 10.1016/j.corsci.2022.110818  

    ISSN: 0010-938X

    eISSN: 1879-0496

  8. Toward the correlation of indentation hardness in micro- and nano-scale: understanding of indentation edge behaviors in Fe-Cr alloys Peer-reviewed

    Diancheng Geng, Hao Yu, Sosuke Kondo, Ryuta Kasada

    JOURNAL OF MATERIALS SCIENCE 57 (28) 13736-13755 2022/07

    DOI: 10.1007/s10853-022-07461-9  

    ISSN: 0022-2461

    eISSN: 1573-4803

  9. Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test Peer-reviewed

    Yuyang Zheng, Diancheng Geng, Hao Yu, Sosuke Kondo, Akihiko Kimura, Hideki Yuya, Ryuta Kasada

    Journal of Nuclear Science and Technology 59 (12) 1507-1518 2022/05

    DOI: 10.1080/00223131.2022.2067258  

    ISSN: 0022-3131

    eISSN: 1881-1248

  10. Practical method to determine the effective zero-point of indentation depth for continuous stiffness measurement nanoindentation test with Berkovich tip Peer-reviewed

    Diancheng Geng, Hao Yu, Yasuki Okuno, Sosuke Kondo, Ryuta Kasada

    Scientific Reports 12 (1) 6391 2022/04/08

    Publisher: Springer Science and Business Media LLC

    DOI: 10.1038/s41598-022-10490-8  

    eISSN: 2045-2322

  11. Effects of zirconium addition on the material properties and microstructure of ODS-Cu alloys Peer-reviewed

    Zimo Gao, Hao Yu, Diancheng Geng, Yuchen Liu, Sosuke Kondo, Yasuki Okuno, Ryuta Kasada

    Journal of Alloys and Compounds 899 163328-163328 2022/04

    DOI: 10.1016/j.jallcom.2021.163328  

    ISSN: 0925-8388

    eISSN: 1873-4669

  12. Radiation tolerance of alumina scale formed on FeCrAl ODS ferritic alloy Peer-reviewed

    Hao Yu, Haoran Wang, Sosuke Kondo, Yasuki Okuno, Ryuta Kasada, Naoko Oono-Hori, Shigeharu Ukai

    Nuclear Materials and Energy 29 101102-101102 2021/12

    DOI: 10.1016/j.nme.2021.101102  

    ISSN: 2352-1791

    eISSN: 2352-1791

  13. Bonding strength evaluation of explosive welding joint of tungsten to ferritic steel using ultra-small testing technologies Peer-reviewed

    Xiangyu Wu, Sosuke Kondo, Hao Yu, Yasuki Okuno, Masami Ando, Hironori Kurotaki, Shigeru Tanaka, Kazuyuki Hokamoto, Ryosuke Ochiai, Satoshi Konishi, Ryuta Kasada

    Materials Science and Engineering: A 826 141995-141995 2021/10

    Publisher: Elsevier BV

    DOI: 10.1016/j.msea.2021.141995  

    ISSN: 0921-5093

  14. Effect of mechanically alloyed sintering aid on sinterability of TiB2 Peer-reviewed

    Yuki Jimba, Sosuke Kondo, Hao Yu, Haoran Wang, Yasuki Okuno, Ryuta Kasada

    Ceramics International 47 (15) 21660-21667 2021/08

    DOI: 10.1016/j.ceramint.2021.04.179  

    ISSN: 0272-8842

    eISSN: 1873-3956

  15. Research on Fusion Reactor Materials and Related Materials using the Dual-Beam Facility for Energy Science and Technology DuET

    Journal of Plasma Fusion Research 97 (7) 403-418 2021/07

    Publisher:

    ISSN: 0918-7928

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

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

    Nuclear Materials and Energy 26 2021/03

    DOI: 10.1016/j.nme.2021.100903  

    eISSN: 2352-1791

  17. Development of nano-oxide particles dispersed alumina scale formed on Zr-added FeCrAl ODS ferritic alloys

    Hao Yu, Sosuke Kondo, Ryuta Kasada, Naoko Oono, Shigenari Hayashi, Shigeharu Ukai

    Nuclear Materials and Energy 25 2020/12

    DOI: 10.1016/j.nme.2020.100798  

    eISSN: 2352-1791

  18. Corrosion behaviour of Al-added high Mn austenitic steels in molten lead bismuth eutectic with saturated and low oxygen concentrations at 450 ℃

    Haoran Wang, Hao Yu, Sosuke Kondo, Nariaki Okubo, Ryuta Kasada

    Corrosion Science 175 2020/10

    DOI: 10.1016/j.corsci.2020.108864  

    ISSN: 0010-938X

  19. 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

    DOI: 10.2320/matertrans.MT-MBW2019005  

    ISSN: 1345-9678

  20. Comparison of D retention for advanced plasma facing materials by D ion implantation Peer-reviewed

    Shingo Okumura, Yuzuka Hoshino, Ayumu Hayakawa, Kenshiro Miura, Fei Sun, Suguru Masuzaki, Makoto Oyaizu, Robert Kolasinski, Chase N. Taylor, Teppei Otsuka, Yuji Hatano, Masashi Shimada, Hao Yu, Ryuta Kasada, Akira Hasegawa, Yasuhisa Oya

    Nuclear Materials and Energy 46 102069-102069 2026/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2026.102069  

    ISSN: 2352-1791

  21. Interfacial microstructure and adhesion evaluation of pre-oxidized alumina scales on FeCrAl ODS alloy under ion irradiation Peer-reviewed

    Hao Yu, Diancheng Geng, Minha Park, Yasuyuki Ogino, Naoko Oono-Hori, Koji Inoue, Sosuke Kondo, Ryuta Kasada, Shigeharu Ukai

    Journal of Nuclear Materials 623 156464 2026/03

    DOI: 10.1016/j.jnucmat.2026.156464  

  22. Effect of WO3 addition on the fabrication of oxide dispersion-strengthened Cu alloys by mechanical alloying of CuYZr alloy powders Peer-reviewed

    Zimo Gao, Hao Yu, Diancheng Geng, Koji Inoue, Yasuyuki Ogino, Sosuke Kondo, Ryuta Kasada

    Nuclear Materials and Energy 46 102060 2026/01

    DOI: 10.1016/j.nme.2026.102060  

  23. Ion-mixing-induced mitigation of swelling and modulus reduction in irradiated SiC fibers Peer-reviewed

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

    JOURNAL OF THE EUROPEAN CERAMIC SOCIETY 45 (14) 2025/11

    DOI: 10.1016/j.jeurceramsoc.2025.117563  

    ISSN: 0955-2219

    eISSN: 1873-619X

  24. Effect of irradiation temperature on the microstructure and hardness of W-0.3Cr alloy after irradiation with 6.4 MeV Fe ions Peer-reviewed

    Jing Wang, Jingxian Sun, Yingying Jia, Yifan Zhang, Yuji Hatano, Diancheng Geng, Katsuya Suzuki, Chang Chen, Laima Luo, Kiyohiro Yabuuchi, Ryuta Kasada

    MATERIALS & DESIGN 259 2025/11

    DOI: 10.1016/j.matdes.2025.114783  

    ISSN: 0264-1275

    eISSN: 1873-4197

  25. Enhanced oxidation resistance of high-manganese austenitic steels through mechanical alloying and oxide-dispersion strengthening Peer-reviewed

    Diancheng Geng, Hao Yu, Yasuyuki Ogino, Sosuke Kondo, Junichi Miyazawa, Ryuta Kasada

    Materials & Design 260 115218 2025/11

    DOI: 10.1016/j.matdes.2025.115218  

  26. Evaluation of the microstructure and adhesion strength of the alloy-film interface of FeCrAl-ODS alloy with self-forming protective alumina films Peer-reviewed

    Joh HASEGAWA, Xiangyu WU, Hao YU, Ryuta KASADA, Kan SAKAMOTO, Naoko OONO-HORI

    Journal of Nuclear Materials 619 156232 2025/10

    DOI: 10.1016/j.jnucmat.2025.156232  

  27. Surface-Driven Anomalies in irradiation Damage: Low swelling in 316LN stainless steel under Gold-Ion irradiation up to 290 dpa Peer-reviewed

    Qianfei Feng, Yupeng Yin, Wentuo Han, Xiaoou Yi, Pingping Liu, Ryuta Kasada, Somei Ohnuki, Farong Wan

    APPLIED SURFACE SCIENCE 703 2025/09/15

    DOI: 10.1016/j.apsusc.2025.163437  

    ISSN: 0169-4332

    eISSN: 1873-5584

  28. Development of new dry dissolution process of poorly soluble beryl and its acceleration effect by microwave heating Peer-reviewed

    Suguru Nakano, Jae-Hwan Kim, Yoshiaki Akatsu, Shota Yokohama, Taehyun Hwang, Yutaka Sugimoto, Ryuta Kasada, Masaru Nakamichi

    Fusion Engineering and Design 212 114860 2025/03

    DOI: 10.1016/j.fusengdes.2025.114860  

  29. Fracture behavior and grain boundary cohesion of alumina scales formed on ion-irradiated FeCrAl-ODS alloy Peer-reviewed

    Hao Yu, Diancheng Geng, Yasuyuki Ogino, Naoko Oono-Hori, Koji Inoue, Sosuke Kondo, Ryuta Kasada, Shigeharu Ukai

    JOURNAL OF NUCLEAR MATERIALS 606 2025/02

    DOI: 10.1016/j.jnucmat.2025.155663  

    ISSN: 0022-3115

    eISSN: 1873-4820

  30. レーザー核融合炉材料—Laser Fusion Reactor Materials—特集 注目のレーザーフュージョンエネルギー

    笠田 竜太

    Optronics : 光技術コーディネートジャーナル 44 (1) 84-88 2025/01

    Publisher: 東京 : オプトロニクス社

    ISSN: 0286-9659

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

    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

  32. Feasibility study on mass-production of oxide dispersion strengthened Cu alloys for the divertor of DEMO fusion reactor Peer-reviewed

    Hao Yu, Toshiki Saito, Zimo Gao, Yasuyuki Ogino, Sosuke Kondo, Ryuta Kasada, Hiroyuki Noto, Yoshimitsu Hishinuma, Suguru Matsuzaki

    Journal of Nuclear Materials 599 (155205) 2024/10

    DOI: 10.1016/J.JNUCMAT.2024.155205  

  33. Effect of Molten Al/Si Impregnation on the Oxidation Resistance of TiB<inf>2</inf> at 1300°C Peer-reviewed

    Koki Wakatabi, Yuki Jimba, Yasuki Okuno, Sosuke Kondo, Hao Yu, Yasuyuki Ogino, Ryuta Kasada

    Materials Transactions 65 (10) 1367-1372 2024/10

    DOI: 10.2320/matertrans.MT-M2024012  

    ISSN: 1345-9678

  34. The Role of Y2O3/Hf Co-Doping on the Microstructure and Tensile Properties of Alumina-Forming Co-Cr-Al-Ni ODS Superalloy Peer-reviewed

    Hao Yu, Sosuke Kondo, Yasuyuki Ogino, Ryuta Kasada

    Materials Transactions 65 (8) 867-875 2024/08

    DOI: 10.2320/matertrans.MT-M2024025  

  35. セラミックスコーティング界面強度評価のための微小試験法の開発 Invited

    宮岸太一, 近藤創介, 笠田竜太

    材料試験技術 = Journal of Material Testing Research Association of Japan 69 82-85 2024/07

  36. ビッカース硬さ100年—100th anniversary of Vickers hardness test—小特集 仙台シンポジウム Invited

    笠田 竜太

    材料試験技術 = Journal of Material Testing Research Association of Japan 69 (3) 82-85 2024/07

    Publisher: 東京 : 日本材料試験技術協会

    ISSN: 0285-2470

  37. Evaluation of the strength of FeCrAl alloy/surface Oxide film interface by micro double-notch shear test Peer-reviewed

    Naoko Oono-Hori, Angela Dannea Anak Andria, Xiangyu Wu, Hao Yu, Ryuta Kasada

    Fusion Engineering and Design 201 2024/04

    DOI: 10.1016/j.fusengdes.2024.114243  

    ISSN: 0920-3796

  38. Mechanism of enhanced room temperature ductility of cold–rolled tungsten under micro-bending test Peer-reviewed

    Xiangyu Wu, Yuki Jimba, Sosuke Kondo, Hao Yu, Yasuyuki Ogino, Akira Hasegawa, Ryuta Kasada

    Materialia 33 101971-101971 2024/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.mtla.2023.101971  

    ISSN: 2589-1529

  39. Contribution of Y<inf>2</inf>O<inf>3</inf>/Hf co-doping to alumina scale growth on oxide dispersion strengthened Co-based superalloy Peer-reviewed

    Hao Yu, Ryuta Kasada, Koji Inoue, Sosuke Kondo, Yasuyuki Ogino, Shigeharu Ukai

    Corrosion Science 227 2024/02

    DOI: 10.1016/j.corsci.2023.111775  

    ISSN: 0010-938X

  40. Ten-Year Recycling of Vanadium Alloy in Fusion Reactors

    Takuya Nagasaka, Teruya Tanaka, Makoto Kobayashi, Ken Ichi Fukumoto, Takeshi Toyama, Takamasa Sugawara, Ryuta Kasada, Yuji Yamauchi, Kazunari Katayama, Makoto Oya, Kiyohiro Yabuuchi, Seiji Sakurai, Kazuhiro Nomura, Hideo Yoshinaga

    Materials Science Forum 1106 117-126 2023/12/05

    Publisher: Trans Tech Publications, Ltd.

    DOI: 10.4028/p-nmm22p  

    eISSN: 1662-9752

    More details Close

    Low-activation characteristics and dominant radioactive isotopes limiting materials recycling were analyzed for a fusion-reactor-grade vanadium alloy, NIFS-HEAT-2. In order to reduce contact dose rate after use in fusion reactors, purification of the base metal vanadium was examined by chemical aqueous separation, electron-beam vacuum melting and zone refining, focusing on the removal of the dominant high-activation impurities, such as Co, Cu, Fe, Nb, Ni and Mo. Based on the measured impurity levels, remote recycling of vanadium alloy is possible within ten years after use in fusion reactors under operation condition with 100 dpa irradiation. Early quasi-hands-on recycling requires further purification and re-design of alloy composition especially with low Ti and high Cr content. The present paper discusses status of material R&amp;Ds for the ten-year recycling and impact on operation of fusion reactors.

  41. High-strength TiB-TiB<inf>2</inf> ceramics fabricated by low-temperature sintering with mechanically milled aids Peer-reviewed

    Yuki Jimba, Yasuki Okuno, Sosuke Kondo, Hao Yu, Yasuyuki Ogino, Shuhei Nogami, Ryuta Kasada

    Ceramics International 49 (22) 34863-34871 2023/11/15

    DOI: 10.1016/j.ceramint.2023.08.160  

    ISSN: 0272-8842

  42. A Trade–off between Mechanical Strength and Conductivity in Oxide Dispersion–Strengthened–Cu Alloys Fabricated by Mechanical Alloying

    Yuchen Liu, Ryuta Kasada, Zimo Gao, Hideaki Yao, Sosuke Kondo, Hao Yu, Satoshi Konishi, Mohammad Aghamiri, Naoko Oono, Shigeharu Ukai, Hiroyuki Noto, Yoshimitsu Hishinuma, Takeo Muroga

    Journal of Japan Institute of Copper 62 (1) 152-157 2023/11

    DOI: 10.34562/jic.62.1_152  

  43. Kinetic study on leaching process of beryl with basic solution under microwave heating Peer-reviewed

    Suguru Nakano, Jae Hwan Kim, Yoshiaki Akatsu, Taehyun Hwang, Yutaka Sugimoto, Ryuta Kasada, Masaru Nakamichi

    Fusion Engineering and Design 196 2023/11

    DOI: 10.1016/j.fusengdes.2023.114014  

    ISSN: 0920-3796

  44. 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

  45. 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

  46. Formation of intermetallic and its effect on the hardening of welding joint between vanadium alloy and Hastelloy X alloy after heat treatment Peer-reviewed

    Shaoning Jiang, Jingjie Shen, Takuya Nagasaka, Takeo Muroga, Akio Sagara, Somei Ohnuki, Kazuyuki Hokamoto, Weifeng Rao, Shigeru Tanaka, Daisuke Inao, Yasuhiro Morizono, Ryuta Kasada, Pengfei Zheng

    Nuclear Materials and Energy 34 2023/03

    DOI: 10.1016/j.nme.2023.101389  

    eISSN: 2352-1791

  47. Influence of Ni content on the oxidation behavior of alumina-forming Co-based oxide dispersion strengthened superalloys at 900 °C Peer-reviewed

    Hao Yu, Sosuke Kondo, Ryuta Kasada, Shigeharu Ukai

    Corrosion Science 212 2023/03

    DOI: 10.1016/j.corsci.2022.110933  

    ISSN: 0010-938X

    eISSN: 1879-0496

  48. Evaluation of equi-biaxial strength of thin sic coatings using ring-on-ring testing and digital image correlation Peer-reviewed

    Sola Iwamoto, Sosuke Kondo, Hirokazu Katsui, Kazuya Shimoda, Hao Yu, Yasuyuki Ogino, Ryuta Kasada

    International Journal of Applied Ceramic Technology 2023

    DOI: 10.1111/ijac.14553  

    ISSN: 1546-542X

    eISSN: 1744-7402

  49. Effect of Ni addition on the microstructure and mechanical properties of Co-Cr-Al oxide dispersion strengthened superalloys Peer-reviewed

    Yu, H., Kondo, S., Kasada, R., Ukai, S.

    Materials Characterization 200 2023

    DOI: 10.1016/j.matchar.2023.112892  

    ISSN: 1044-5803

  50. 超微小試験技術による材料機械的強度特性の取得方法 Invited

    笠田竜太

    応用物理 91 (12) 760-764 2022/12

    DOI: 10.11470/oubutsu.91.12_760  

  51. Effects of titanium concentration on microstructure and mechanical properties of high-purity vanadium alloys Peer-reviewed

    Jingjie Shen, Takuya Nagasaka, Masayuki Tokitani, Takeo Muroga, Ryuta Kasada, Seiji Sakurai

    Materials &amp; Design 224 111390-111390 2022/12

    Publisher: Elsevier BV

    DOI: 10.1016/j.matdes.2022.111390  

    ISSN: 0264-1275

  52. Electronic descriptors for vacancy formation and hydrogen solution in Be-rich intermetallics Peer-reviewed

    Keisuke Mukai, Ryuta Kasada, Jae-Hwan Kim, Masaru Nakamichi

    Acta Materialia 241 118428-118428 2022/12

    Publisher: Elsevier BV

    DOI: 10.1016/j.actamat.2022.118428  

    ISSN: 1359-6454

  53. Compressive strength degradation of SiC fibers exposed to high temperatures due to impurity-induced internal oxidation Peer-reviewed

    Xinwei Yuan, Sosuke Kondo, Kazuya Shimoda, Hao Yu, Yasuki Okuno, Ryuta Kasada

    Journal of the European Ceramic Society 42 (13) 5334-5342 2022/10

    DOI: 10.1016/j.jeurceramsoc.2022.06.051  

    ISSN: 0955-2219

    eISSN: 1873-619X

  54. Hybrid Organic-Inorganic Perovskite Semiconductor-Based High-Flux Neutron Detector with BN Converter Peer-reviewed

    Yasuki Okuno, Taisuke Matsui, Tomohiro Kobayashi, Mitsuru Imaizumi, Yuki Jimba, Yu Hao, Sosuke Kondo, Yukihiro Kaneko, Ryuta Kasada

    ACS Applied Electronic Materials 4 (7) 3411-3420 2022/07/26

    DOI: 10.1021/acsaelm.2c00258  

    eISSN: 2637-6113

  55. Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy

    Takeshi Miyazawa, Haruka Saito, Yoshimitsu Hishinuma, Takuya Nagasaka, Takeo Muroga, Jingjie Shen, Yasuki Okuno, Hao Yu, Ryuta Kasada, Akira Hasegawa

    Nuclear Materials and Energy 31 101198-101198 2022/06

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2022.101198  

    ISSN: 2352-1791

  56. Change in nanoindentation hardness of polycrystalline tungsten irradiated with Fe ions or electrons by hydrogen gas charging Peer-reviewed

    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

  57. Dissolution and recovery of beryllium from beryl using a novel wet process with microwave heating Peer-reviewed

    Suguru Nakano, Jae-Hwan Kim, Taehyun Hwang, Ryuta Kasada, Masaru Nakamichi

    Nuclear Materials and Energy 30 101113-101113 2022/03

    Publisher: Elsevier BV

    DOI: 10.1016/j.nme.2022.101113  

    ISSN: 2352-1791

  58. Nuclear Fusion 誌のアブストラクトの統計的解析による核融合科学分野の研究動向の調査の試み Peer-reviewed

    坂東隆宏, 笠田竜太, 小南理恵

    プラズマ・核融合学会誌 97 (3) 149-153 2021/03

  59. Contribution of dangling-bonds to polycrystalline SiC corrosion

    Sosuke Kondo, Kotaro Seki, Yuki Maeda, Hao Yu, Kazuhiro Fukami, Ryuta Kasada

    Scripta Materialia 188 6-9 2020/11

    DOI: 10.1016/j.scriptamat.2020.07.001  

    ISSN: 1359-6462

  60. Fuel flow and stock during deuterium-deuterium start-up of fusion reactor with advanced plasma model

    Kento Miyamae, H. Yamada, R. Kasada, S. Konishi, R. Sakamoto

    Fusion Engineering and Design 160 2020/11

    DOI: 10.1016/j.fusengdes.2020.111794  

    ISSN: 0920-3796

  61. Correction to: Economic Analysis Between Diesel and SOFC Electricity via Fusion-Biomass Hybrid Model (Journal of Fusion Energy, (2018), 37, 6, (333-345), 10.1007/s10894-018-0192-z)

    Hoseok Nam, Ryuta Kasada, Satoshi Konishi

    Journal of Fusion Energy 39 (5) 297-298 2020/10

    DOI: 10.1007/s10894-020-00267-0  

    ISSN: 0164-0313

    eISSN: 1572-9591

  62. Interfacial characterization of dissimilar-metals bonding between vanadium alloy and Hastelloy X alloy by explosive welding Peer-reviewed

    Shaoning Jiang, Jingjie Shen, Takuya Nagasaka, Takeo Muroga, Akio Sagara, Somei Ohnuki, Kazuyuki Hokamoto, Shigeru Tanaka, Daisuke Inao, Yasuhiro Morizono, Ryuta Kasada, Pengfei Zheng

    Journal of Nuclear Materials 539 2020/10

    DOI: 10.1016/j.jnucmat.2020.152322  

    ISSN: 0022-3115

  63. The size dependence of microstructure and hardness on the MA powders for the MA-HIP processed Cu-Y<inf>2</inf>O<inf>3</inf> dispersion-strengthened alloys

    Bing Ma, Yoshimitsu Hishinuma, Yusuke Shimada, Hiroyuki Noto, Ryuta Kasada, Naoko Oono, Shigeharu Ukai, Takeo Muroga

    Nuclear Materials and Energy 24 2020/08

    DOI: 10.1016/j.nme.2020.100773  

    eISSN: 2352-1791

  64. Fabrication and mechanical properties of tungsten carbide thin films via mist chemical vapor deposition Peer-reviewed

    Takumi Ikenoue, Takuji Yoshida, Masao Miyake, Ryuta Kasada, Tetsuji Hirato

    Journal of Alloys and Compounds 829 2020/07/15

    DOI: 10.1016/j.jallcom.2020.154567  

    ISSN: 0925-8388

  65. 特集記事:「核融合エネルギー開発の現状」(3)核融合エネルギーの開発計画

    岡野邦彦, 笠田竜太

    保全学 19 (2) 10-15 2020/07/10

  66. Chemical State Analysis of Light Elements in Nuclear Fission and Fusion Reactor Materials by Soft X-ray Emission Spectroscopy in Electron Probe Microanalyzer Invited

    Ryuta KASADA, Keisuke MUKAI

    JEOL News 55 (1) 32-35 2020/07

  67. 軟X線発光分光装置を搭載した電子プローブマイクロアナライザによる原子力・核融合材料中の軽元素分析および状態分析 Invited

    笠田竜太, 向井啓祐

    日本電子news 52 (1) 19-22 2020/05

  68. Occupied Electronic States of Li in Li, Li2O2, and Li2O Analyzed by Soft X-ray Emission Spectroscopy Peer-reviewed

    Keisuke Mukai, Ryuta Kasada, Kazuya Sasaki, Satoshi Konishi

    The Journal of Physical Chemistry C 2020/04/14

    DOI: 10.1021/acs.jpcc.0c02885  

    ISSN: 1932-7455

  69. Microstructure development in cryogenically rolled oxide dispersion strengthened copper Peer-reviewed

    S. M.S. Aghamiri, S. H. Zhang, S. Ukai, N. Oono, R. Kasada, H. Noto, Y. Hishinuma, T. Muroga

    Materialia 9 2020/03

    DOI: 10.1016/j.mtla.2019.100520  

    eISSN: 2589-1529

  70. Contribution of Crystal Lattice Defects to Polycrystalline SiC Corrosion

    Sosuke Kondo, Kotaro Seki, Yuki Maeda, Hao Yu, Kazuhiro Fukami, Ryuta Kasada

    SSRN Electronic Journal 2020

    Publisher: Elsevier {BV}

    DOI: 10.2139/ssrn.3603594  

    ISSN: 1556-5068

  71. Positron annihilation study on the phase transition of thermally aged Fe-Cr binary alloys at 748K Peer-reviewed

    R. Kasada, K. Sato

    Philosophical Magazine Letters 99 (10) 360-371 2019/10/03

    DOI: 10.1080/09500839.2019.1695070  

    ISSN: 0950-0839

    eISSN: 1362-3036

  72. Recrystallization of cold rolled oxide dispersion strengthened copper during room temperature annealing Peer-reviewed

    S. M.S. Aghamiri, S. Ukai, N. Oono, R. Kasada, H. Noto, Y. Hishinuma, T. Muroga

    Journal of Alloys and Compounds 798 187-193 2019/08/25

    DOI: 10.1016/j.jallcom.2019.05.248  

    ISSN: 0925-8388

  73. Micro- and macro- elastic properties of tungsten fiber-reinforced tungsten composites probed by nano-indentation and laser ultrasonics Peer-reviewed

    H. T. Lee, S. Ando, J. W. Coenen, Y. Mao, R. Kasada, J. Riesch, Y. Ueda

    Nuclear Materials and Energy 19 262-266 2019/05

    DOI: 10.1016/j.nme.2019.03.001  

    eISSN: 2352-1791

  74. 核融合工学のこれまでと,これから

    笠田竜太

    日本原子力学会誌 61 (4) 257-258 2019/04

  75. Valence Electron and Chemical State Analysis of Be<inf>12</inf>M (M = Ti, V) Beryllides by Soft X-ray Emission Spectroscopy Peer-reviewed

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

    ACS Applied Energy Materials 2 (4) 2889-2895 2019/04

    DOI: 10.1021/acsaem.9b00223  

    eISSN: 2574-0962

  76. Microstructure development and high tensile properties of He/H<inf>2</inf> milled oxide dispersion strengthened copper Peer-reviewed

    S. M.S. Aghamiri, N. Oono, S. Ukai, R. Kasada, H. Noto, Y. Hishinuma, T. Muroga

    Journal of Alloys and Compounds 783 674-679 2019/04

    DOI: 10.1016/j.jallcom.2018.12.298  

    ISSN: 0925-8388

  77. Brass-texture induced grain structure evolution in room temperature rolled ODS copper Peer-reviewed

    S. M.S. Aghamiri, N. Oono, S. Ukai, R. Kasada, H. Noto, Y. Hishinuma, T. Muroga

    Materials Science and Engineering A 749 118-128 2019/03/11

    DOI: 10.1016/j.msea.2019.02.019  

    ISSN: 0921-5093

  78. Investigation of mechanical properties of stress-relieved and electron-irradiated tungsten after hydrogen charging Peer-reviewed

    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

  79. Japanese activities of the R&amp;D on silicon carbide composites in the broader approach period and beyond Peer-reviewed

    Takashi Nozawa, Kazumi Ozawa, Chang Ho Park, Joon Soo Park, Akira Kohyama, Akira Hasegawa, Shuhei Nogami, Tatsuya Hinoki, Sosuke Kondo, Toyohiko Yano, Tamaki Shibayama, Bun Tsuchiya, Tatsuo Shikama, Shinji Nagata, Teruya Tanaka, Hirotomo Iwakiri, Yasushi Yamamoto, Satoshi Konishi, Ryuta Kasada, Masatoshi Kondo, Tomoaki Kunugi, Takehiko Yokomine, Yoshitaka Ueki, Nariaki Okubo, Tomitsugu Taguchi, Hiroyasu Tanigawa

    Journal of Nuclear Materials 511 582-590 2018/12/01

    DOI: 10.1016/j.jnucmat.2018.05.045  

    ISSN: 0022-3115

  80. Economic Analysis Between Diesel and SOFC Electricity via Fusion-Biomass Hybrid Model Peer-reviewed

    Hoseok Nam, Ryuta Kasada, Satoshi Konishi

    Journal of Fusion Energy 37 (6) 333-345 2018/12/01

    DOI: 10.1007/s10894-018-0192-z  

    ISSN: 0164-0313

  81. Liquid PbLi atomization in vacuum for tritium and heat recovery Peer-reviewed

    Fumito Okino, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 136 63-66 2018/11

    DOI: 10.1016/j.fusengdes.2017.12.025  

    ISSN: 0920-3796

  82. The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C Peer-reviewed

    Chang Ho Park, Takashi Nozawa, Ryuta Kasada, Silvano Tosti, Satoshi Konishi, Hiroyasu Tanigawa

    Fusion Engineering and Design 136 623-627 2018/11

    DOI: 10.1016/j.fusengdes.2018.03.042  

    ISSN: 0920-3796

  83. An action plan of Japan toward development of demo reactor Peer-reviewed

    Kunihiko Okano, Ryuta Kasada, Yasushi Ikebe, Yasutomo Ishii, Kyoko Oba, Mieko Kashiwagi, Ryuichi Sakamoto, Naoki Sawa, Hidenobu Takenaga, Arata Nishimura, Masaru Fukuie, Shinsuke Fujioka, Yoshio Ueda, Tsuyoshi Akiyama

    Fusion Engineering and Design 136 183-189 2018/11

    DOI: 10.1016/j.fusengdes.2018.01.040  

    ISSN: 0920-3796

  84. Validation of miniature test specimens for post-irradiation thermal diffusivity measurement Peer-reviewed

    Masafumi Akiyoshi, Ryuta Kasada, Yuko Ishibashi, Lauren M. Garrison, Josina W. Geringer, Wallace D. Porter, Yutai Katoh

    Fusion Engineering and Design 136 513-517 2018/11

    DOI: 10.1016/j.fusengdes.2018.03.008  

    ISSN: 0920-3796

  85. In-situ fabrication of yttria dispersed copper alloys through MA-HIP process Peer-reviewed

    B. Huang, Y. Hishinuma, H. Noto, R. Kasada, N. Oono, S. Ukai, T. Muroga

    Nuclear Materials and Energy 16 168-174 2018/08

    DOI: 10.1016/j.nme.2018.06.024  

    eISSN: 2352-1791

  86. Plasma control requirements for commercial fusion power plants: A quantitative scenario analysis with a dynamic fusion power plant model Peer-reviewed

    Shutaro Takeda, Shigeki Sakurai, Ryuta Kasada, Satoshi Konishi

    IEEE Transactions on Plasma Science 46 (5) 1205-1210 2018/05

    DOI: 10.1109/TPS.2018.2794560  

    ISSN: 0093-3813

  87. Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application Peer-reviewed

    S. M.S. Aghamiri, N. Oono, S. Ukai, R. Kasada, H. Noto, Y. Hishinuma, T. Muroga

    Nuclear Materials and Energy 15 17-22 2018/05

    DOI: 10.1016/j.nme.2018.05.019  

    eISSN: 2352-1791

  88. Detection of phase separation of neutron-irradiated Fe–Cr binary alloys using positron annihilation spectroscopy Peer-reviewed

    Y. Noshita, K. Sato, H. Yamashita, R. Kasada, Q. Xu, M. Hatakeyama, S. Sunada

    Nuclear Materials and Energy 15 175-179 2018/05

    DOI: 10.1016/j.nme.2018.04.007  

    eISSN: 2352-1791

  89. Effects of milling parameters on the microstructure and Charpy impact properties of MA/ODS ferritic steels Peer-reviewed

    Noriyuki Y. Iwata, Ryuta Kasada, Akihiko Kimura, Takanari Okuda

    Fusion Engineering and Design 126 24-28 2018/01

    DOI: 10.1016/j.fusengdes.2017.10.025  

    ISSN: 0920-3796

  90. Electrodeposition of aluminumtungsten alloy films using EMICAlCl<inf>3</inf>W<inf>6</inf>Cl<inf>12</inf> ionic liquids of different compositions Peer-reviewed

    Shota Higashino, Masao Miyake, Hisashi Fujii, Ayumu Takahashi, Ryuta Kasada, Tetsuji Hirato

    Materials Transactions 59 (6) 944-949 2018

    DOI: 10.2320/matertrans.M2018051  

    ISSN: 1345-9678

  91. Application of small specimen test technique to evaluate fracture toughness of reduced activation ferritic/martensitic steel Peer-reviewed

    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

  92. Myth of initial loading tritium for DEMO—Modelling of fuel system and operation scenario Peer-reviewed

    Satoshi Konishi, Ryuta Kasada, Fumito Okino

    Fusion Engineering and Design 121 111-116 2017/10

    DOI: 10.1016/j.fusengdes.2017.05.138  

    ISSN: 0920-3796

  93. Evaluation of the hardness and Young's modulus of electrodeposited Al–W alloy films by nano-indentation Peer-reviewed

    Shota Higashino, Masao Miyake, Ayumu Takahashi, Yuya Matamura, Hisashi Fujii, Ryuta Kasada, Tetsuji Hirato

    Surface and Coatings Technology 325 346-351 2017/09/25

    DOI: 10.1016/j.surfcoat.2017.06.064  

    ISSN: 0257-8972

  94. Tritium recovery efficiency from an array of PbLi droplets in vacuum Peer-reviewed

    Fumito Okino, Laetitia Frances, David Demange, Ryuta Kasada, Satoshi Konishi

    Fusion Science and Technology 71 (4) 575-583 2017/05

    DOI: 10.1080/15361055.2017.1290972  

    ISSN: 1536-1055

  95. TEM and HRTEM study of oxide particles in an Al-alloyed high-Cr oxide dispersion strengthened ferritic steel with Hf addition Peer-reviewed

    Peng Dou, Akihiko Kimura, Ryuta Kasada, Takanari Okuda, Masaki Inoue, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa, Fujio Abe, Shan Jiang, Zhigang Yang

    Journal of Nuclear Materials 485 189-201 2017/03/01

    DOI: 10.1016/j.jnucmat.2016.12.001  

    ISSN: 0022-3115

  96. Longitudinal and shear wave velocities in pure tungsten and tungsten fiber-reinforced tungsten composites Peer-reviewed

    H. T. Lee, S. Ando, J. W. Coenen, Y. Mao, J. Riesch, H. Gietl, R. Kasada, Y. Hamaji, K. Ibano, Y. Ueda

    Physica Scripta 2017 (T170) 2017

    DOI: 10.1088/1402-4896/aa89c7  

    ISSN: 0031-8949

    eISSN: 1402-4896

  97. Feasibility of waste to bio-diesel production via nuclear-biomass hybrid model; system dynamics analysis Peer-reviewed

    Hoseok Nam, Ryuta Kasada, Satoshi Konishi

    2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017

  98. Environmental life cycle assessment of high temperature nuclear fission and fusion biomass gasification plants Peer-reviewed

    Shutaro Takeda, Shigeki Sakurai, Ryuta Kasada, Satoshi Konishi

    2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017

  99. Evaluation of ion-irradiation hardening of tungsten single crystals by nanoindentation technique considering material pile-up effect Peer-reviewed

    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

  100. Ion-irradiation effect on strain rate sensitivity of nanoindentation hardness of W single crystal Peer-reviewed

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

    Materials Transactions 58 (4) 580-586 2017

    DOI: 10.2320/matertrans.ML201603  

    ISSN: 1345-9678

  101. Study on the characteristics of thermal structural response of full tungsten divertor under ELM-like heat pulse Peer-reviewed

    Hyoseong Gwon, Shinzaburo Matsuda, Ryuta Kasada, Satoshi Konishi, Yoshinori Kawamura

    Fusion Engineering and Design 109-111 1697-1700 2016/11/01

    DOI: 10.1016/j.fusengdes.2015.10.027  

    ISSN: 0920-3796

  102. Improvement of system code importing evaluation of Life Cycle Analysis of tokamak fusion power reactors Peer-reviewed

    Hikaru Kobori, Ryuta Kasada, Ryoji Hiwatari, Satoshi Konishi

    Fusion Engineering and Design 109-111 760-763 2016/11/01

    DOI: 10.1016/j.fusengdes.2016.02.004  

    ISSN: 0920-3796

  103. Improvement of tensile properties of pure Cu and CuCrZr alloy by cryo-rolling process Peer-reviewed

    Ryota Ihira, Hyoseong Gwon, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 109-111 485-488 2016/11/01

    DOI: 10.1016/j.fusengdes.2016.02.070  

    ISSN: 0920-3796

  104. Limitation of fusion power plant installation on future power grids under the effect of renewable and nuclear power sources Peer-reviewed

    Shutaro Takeda, Shigeki Sakurai, Yasushi Yamamoto, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 109-111 1754-1758 2016/11/01

    DOI: 10.1016/j.fusengdes.2015.10.003  

    ISSN: 0920-3796

  105. Chemical state mapping of degraded B<inf>4</inf>C control rod investigated with soft X-ray emission spectrometer in electron probe micro-analysis Peer-reviewed

    R. Kasada, Y. Ha, T. Higuchi, K. Sakamoto

    Scientific Reports 6 2016/05/10

    DOI: 10.1038/srep25700  

    eISSN: 2045-2322

  106. Development of Strategic Establishment of Technology Bases for a Fusion DEMO Reactor in Japan Peer-reviewed

    Hiroshi Yamada, Ryuta Kasada, Akira Ozaki, Ryuichi Sakamoto, Yoshiteru Sakamoto, Hidenobu Takenaga, Teruya Tanaka, Hisashi Tanigawa, Kunihiko Okano, Kenji Tobita, Osamu Kaneko, Kenkichi Ushigusa

    Journal of Fusion Energy 35 (1) 4-26 2016/02/01

    DOI: 10.1007/s10894-015-0018-1  

    ISSN: 0164-0313

  107. SSTT Development Towards to The Design of Fusion DEMO Reactors and Future Direction Plan Peer-reviewed

    E. Wakai, S. Nogami, Y. Ito, A. Kimura, H. Tanigawa, M. Sugimoto, M. Ando, A. Hasegawa, A. Nishimura, R. Kasada, M. Saito, F. Arbeiter, J. Knaster, S.M. Gonzalez, de Vicente

    26th IAEA Fusion Energy Conference 2016 MPT/P5-25-(pages 8) 2016

    DOI: 10.1007/s10894-015-0018-1  

  108. Let's Create our Future with Fusion Reactor

    KASADA Ryuta

    Journal of the Society of Mechanical Engineers 119 (1174) 510-513 2016

    Publisher: The Japan Society of Mechanical Engineers

    DOI: 10.1299/jsmemag.119.1174_510  

    ISSN: 0021-4728

  109. Japanese endeavors to establish technological bases for DEMO

    Hiroshi Yamada, Ryuta Kasada, Akira Ozaki, Ryuichi Sakamoto, Yoshiteru Sakamoto, Hidenobu Takenaga, Teruya Tanaka, Hisashi Tanigawa, Kunihiko Okano, Kenji Tobita, Osamu Kaneko, Kenkichi Ushigusa

    Fusion Engineering and Design 109-111 1318-1325 2016

    DOI: 10.1016/j.fusengdes.2015.12.035  

    ISSN: 0920-3796

  110. Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system Peer-reviewed

    Fumito Okino, Pattrick Calderoni, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 109-111 (Part B) 1748-1753 2016

    DOI: 10.1016/j.fusengdes.2015.10.004  

    ISSN: 0920-3796

  111. Evaluation of strain-rate sensitivity of ion-irradiated austenitic steel using strain-rate jump nanoindentation tests Peer-reviewed

    Ryuta Kasada, Satoshi Konishi, Dai Hamaguchi, Masami Ando, Hiroyasu Tanigawa

    Fusion Engineering and Design 109-111 1507-1510 2016

    DOI: 10.1016/j.fusengdes.2015.11.041  

    ISSN: 0920-3796

  112. Oxide dispersion strengthened steels for advanced blanket systems Peer-reviewed

    Akihiko Kimura, Wentuo Han, Hwanil Je, Kiyohiro Yabuuchi, Ryuta Kasada

    Plasma and Fusion Research 11 (1) 2016

    DOI: 10.1585/pfr.11.2505090  

    eISSN: 1880-6821

  113. Dynamic tensile properties of reduced-activation ferritic steel F82H Peer-reviewed

    Ryuta Kasada, Daiki Ishii, Masami Ando, Hiroyasu Tanigawa, Mitsuru Ohata, Satoshi Konishi

    Fusion Engineering and Design 100 146-151 2015/11/01

    DOI: 10.1016/j.fusengdes.2015.05.001  

    ISSN: 0920-3796

  114. Evaluation of tritium transport in the biomass-fusion hybrid system and its environmental impact Peer-reviewed

    Kyosuke Namba, Ryuta Kasada, Satoshi Konishi, Yasushi Yamamoto

    Fusion Engineering and Design 98-99 2162-2165 2015/10/01

    DOI: 10.1016/j.fusengdes.2015.07.009  

    ISSN: 0920-3796

  115. Evaluation of thermal structural behavior of divertor under ELM Peer-reviewed

    Hyoseong Gwon, Shinzaburo Matsuda, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 98-99 1318-1322 2015/10/01

    DOI: 10.1016/j.fusengdes.2015.02.015  

    ISSN: 0920-3796

  116. A system dynamics model for stock and flow of tritium in fusion power plant Peer-reviewed

    Ryuta Kasada, Saerom Kwon, Satoshi Konishi, Yoshiteru Sakamoto, Toshihiko Yamanishi, Kenji Tobita

    Fusion Engineering and Design 98-99 1804-1807 2015/10/01

    DOI: 10.1016/j.fusengdes.2015.03.047  

    ISSN: 0920-3796

  117. Dynamic simulation-based case study of fusion on small-scale electrical grids Peer-reviewed

    Shutaro Takeda, Satoshi Konishi, Yasushi Yamamoto, Ryuta Kasada, Shigeki Sakurai

    Fusion Science and Technology 68 (2) 341-345 2015/09/01

    DOI: 10.13182/FST15-106  

    ISSN: 1536-1055

    eISSN: 1943-7641

  118. 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

  119. Round-Table Discussion : Current Status and Challenges of Nuclear Fusion Research toward Development Phase of a DEMO Reactor

    WATANABE Kazuhito, KIKUCHI Koichi, SEMBA Hideshi, IKEBE Yasushi, TANIGAWA Hisashi, OCHIAI Kentaro, TANIGAWA Hiroyasu, NAKAMURA Makoto, MIYAZAWA Junichi, NOGAMI Shuhei, MATSUNAGA Go, YAMANOI Kohei, KASADA Ryuta

    プラズマ・核融合学会誌 91 (3) 215-230 2015/03

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  120. Effects of tensile stress on Cu clustering in irradiated Fe-Cu alloy Peer-reviewed

    K. Fujii, K. Fukuya, R. Kasada, A. Kimura, T. Ohkubo

    Journal of Nuclear Materials 458 281-287 2015/03

    DOI: 10.1016/j.jnucmat.2014.12.108  

    ISSN: 0022-3115

  121. Current Status of Internet Outreach and Fusion Portal Web Site

    KASADA Ryuta

    プラズマ・核融合学会誌 91 (2) 111-114 2015/02

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

    More details Close

    インターネットにおける核融合の状況を分析し,よりよいインターネットアウトリーチの方向性について論じる.得られた分析結果から,インターネットにおける一般的な情報の入手先として,Wikipediaが重要な役割を果たしているため,情報の質の向上のために専門家が関与する必要があることを指摘した.また,アウトリーチの基本である双方向性を高めるために,核融合ポータルサイトの設置が有効な手段であることを示した.

  122. Requirements for DEMO from the Aspect of Mitigation of Adverse Effects on the Electrical Grid Peer-reviewed

    Shutaro TAKEDA, Yasushi YAMAMOTO, Ryuta KASADA, Shigeki SAKURAI, Satoshi KONISHI

    Plasma and Fusion Research 10 1205070-1205070 2015

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

    DOI: 10.1585/pfr.10.1205070  

    More details Close

    <p>The adverse effects of DEMO on the future electrical grid due to sudden output interruptions, such as disruptions, were analyzed quantitatively. The results indicated that when considerable percentage of renewables are installed, the power system would experience serious frequency deviations as large as 0.4 Hz, which is greater than the current tolerance, 0.2 Hz. DEMO installation would need an assessment as part of the power system, together with mitigation devices, to be connected to the grid.</p>

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

    木村 晃彦, 檜木 達也, 笠田 竜太

    加速器 : 日本加速器学会誌 12 (4) 217-221 2015

    Publisher: 日本加速器学会

    ISSN: 1349-3833

  124. Evaluation of irradiation hardening of ion-irradiated V-4Cr-4Ti and V-4Cr-4Ti-0.15Y alloys by nanoindentation techniques Peer-reviewed

    Takeshi Miyazawa, Takuya Nagasaka, Ryuta Kasada, Yoshimitsu Hishinuma, Takeo Muroga, Hideo Watanabe, Takuya Yamamoto, Shuhei Nogami, Masahiko Hatakeyama

    Journal of Nuclear Materials 455 (1-3) 440-444 2014/12

    DOI: 10.1016/j.jnucmat.2014.07.059  

    ISSN: 0022-3115

  125. Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus Peer-reviewed

    A. Kanai, R. Kasada, M. Nakajima, T. Hirose, H. Tanigawa, M. Enoeda, S. Konishi

    Journal of Nuclear Materials 455 (1-3) 431-435 2014/12

    DOI: 10.1016/j.jnucmat.2014.07.067  

    ISSN: 0022-3115

  126. Evaluation of heat transfer by sublimation for the application to the divertor heat sink for high fusion energy conversion Peer-reviewed

    Hyoseong Gwon, Yuto Takeuchi, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 89 (7-8) 1003-1008 2014/10

    DOI: 10.1016/j.fusengdes.2014.03.041  

    ISSN: 0920-3796

  127. Compatibility of Ni and F82H with liquid Pb-Li under rotating flow Peer-reviewed

    A. Kanai, C. Park, K. Noborio, R. Kasada, S. Konishi, T. Hirose, T. Nozawa, H. Tanigawa

    Fusion Engineering and Design 89 (7-8) 1653-1657 2014/10

    DOI: 10.1016/j.fusengdes.2014.03.008  

    ISSN: 0920-3796

  128. Study on flow instability for feasibility of a thin liquid film first wall Peer-reviewed

    Fumito Okino, Ryuta Kasada, Satoshi Konishi

    Fusion Engineering and Design 89 (7-8) 1054-1058 2014/10

    DOI: 10.1016/j.fusengdes.2014.01.047  

    ISSN: 0920-3796

  129. Underwater explosive welding of tungsten to reduced-activation ferritic steel F82H Peer-reviewed

    Daichi Mori, Ryuta Kasada, Satoshi Konishi, Yasuhiro Morizono, Kazuyuki Hokamoto

    Fusion Engineering and Design 89 (7-8) 1086-1090 2014/10

    DOI: 10.1016/j.fusengdes.2013.12.038  

    ISSN: 0920-3796

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

    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

  131. Interfacial microstructures and hardness distributions of vacuum plasma spraying W-coated ODS ferritic steels for fusion plasma facing applications Peer-reviewed

    Sanghoon Noh, Ryuta Kasada, Akihiko Kimura, Takuya Nagasaka, Mikhail A. Sokolov, Tae Kyu Kim

    Fusion Engineering and Design 89 (4) 289-293 2014/04

    DOI: 10.1016/j.fusengdes.2014.01.084  

    ISSN: 0920-3796

  132. Evaluation of irradiation hardening of proton irradiated stainless steels by nanoindentation Peer-reviewed

    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

  133. TEM and HRTEM study of oxide particles in an Al-alloyed high-Cr oxide dispersion strengthened steel with Zr addition Peer-reviewed

    Peng Dou, Akihiko Kimura, Ryuta Kasada, Takanari Okuda, Masaki Inoue, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa, Fujio Abe

    Journal of Nuclear Materials 444 (1-3) 441-453 2014

    DOI: 10.1016/j.jnucmat.2013.10.028  

    ISSN: 0022-3115

  134. Super ODS steels R&D for fuel cladding of advanced nuclear systems Peer-reviewed

    A. Kimura, R. Kasada, N.Y. Iwata, J. Isselin, P. Dou, J.H. Lee, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, H.Sano, T. Fujisawa, F. Abe

    Proceedings of the 2nd International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-2), Daejon, Korea 135-147 2013/12

    DOI: 10.1787/9789264992092-en  

    ISSN: 1990-0643

  135. Influence of processing parameters on the microstructure and Charpy impact properties of ODS ferritic steels Peer-reviewed

    N.Y. Iwata, T. Liu, R. Kasada, A. Kimura, T. Okuda, M. Inoue, F. Abe, S. Ukai, S. Ohnuki, T. Fujisawa

    Proceedings of the 2nd International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-2), Daejon, Korea 367-368 2013/12

  136. Development of high-grade VPS-tungsten coatings on F82H reduced activation steel

    Tomonori Tokunaga, Hideo Watanabe, Naoaki Yoshida, Takuya Nagasaka, Ryuta Kasada, Young-Ju Lee, Akihiko Kimura, Masayuki Tokitani, Masatoshi Mitsuhara, Tatsuya Hinoki, Hideharu Nakashima, Suguru Masuzaki, Takeshi Takabatake, Nobuyoshi Kuroki, Koichiro Ezato, Satoshi Suzuki, Masato Akiba

    JOURNAL OF NUCLEAR MATERIALS 442 (1-3) S287-S291 2013/11

    DOI: 10.1016/j.jnucmat.2012.11.004  

    ISSN: 0022-3115

    eISSN: 1873-4820

  137. 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

  138. Behavior of deuterium retention and surface morphology for VPS-W/F82H

    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) S242-S245 2013/11

    DOI: 10.1016/j.jnucmat.2013.01.321  

    ISSN: 0022-3115

    eISSN: 1873-4820

  139. Application of master curve method to the evaluation of fracture toughness of F82H steels

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura, Eiichi Wakai, Hiroyasu Tanigawa

    JOURNAL OF NUCLEAR MATERIALS 442 (1-3) S38-S42 2013/11

    DOI: 10.1016/j.jnucmat.2013.03.079  

    ISSN: 0022-3115

    eISSN: 1873-4820

  140. 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

  141. Grain refinement of transient liquid phase bonding zone using ODS insert foil

    Hiroyuki Noto, Ryuta Kasada, Akihiko Kimura, Shigeharu Ukai

    JOURNAL OF NUCLEAR MATERIALS 442 (1-3) S567-S571 2013/11

    DOI: 10.1016/j.jnucmat.2013.04.054  

    ISSN: 0022-3115

    eISSN: 1873-4820

  142. Comparison of irradiation hardening and microstructure evolution in ion-irradiated delta and epsilon hydrides

    Naoko Oono, Ryuta Kasada, Toru Higuchi, Kan Sakamoto, Masafumi Nakatsuka, Akiko Hasegawa, Sosuke Kondo, Noriyuki Y. Iwata, Hideki Matsui, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 442 (1-3) S826-S829 2013/11

    DOI: 10.1016/j.jnucmat.2013.03.013  

    ISSN: 0022-3115

    eISSN: 1873-4820

  143. Neutronics and pumping power analyses on the Tokamak reactor for the fusion-biomass hybrid concept

    Kenzo Ibano, Ryuta Kasada, Yasushi Yamamoto, Satoshi Konishi

    FUSION ENGINEERING AND DESIGN 88 (11) 2881-2884 2013/11

    DOI: 10.1016/j.fusengdes.2013.05.088  

    ISSN: 0920-3796

    eISSN: 1873-7196

  144. Effect of nickel content on the neutron irradiation embrittlement of Ni-Mo-Cr steels

    Chang-Hoon Lee, R. Kasada, A. Kimura, Bong-Sang Lee, Dong-Woo Suh, Hu-Chul Lee

    METALS AND MATERIALS INTERNATIONAL 19 (6) 1203-1208 2013/11

    DOI: 10.1007/s12540-013-6007-x  

    ISSN: 1598-9623

    eISSN: 2005-4149

  145. 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

  146. Sol-gel composite coatings as anti-corrosion barrier for structural materials of lead-bismuth eutectic cooled fast reactor

    Ryuta Kasada, Peng Dou

    JOURNAL OF NUCLEAR MATERIALS 440 (1-3) 647-653 2013/09

    DOI: 10.1016/j.jnucmat.2013.06.014  

    ISSN: 0022-3115

    eISSN: 1873-4820

  147. NEUTRONICS ANALYSIS ON THE BEAM OPTICS FROM CYLINDICAL DISCHARGE TYPE FUSION DEVICE

    Naoya Matsui, Takahiro Maegawa, Kazuyuki Noborio, Ryuta Kasada, Yasushi Yamamoto, Satoshi Konishi

    FUSION SCIENCE AND TECHNOLOGY 64 (3) 692-696 2013/09

    ISSN: 1536-1055

  148. Deuterium retention in VPS-W coated vanadium alloy (V-4Cr-4Ti)

    Yoshio Ueda, Kazuhiro Uekita, Makoto Oya, Yusuke Ohtsuka, Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura, Tomonori Tokunaga, Naoaki Yoshida

    JOURNAL OF NUCLEAR MATERIALS 438 S1125-S1128 2013/07

    DOI: 10.1016/j.jnucmat.2013.01.248  

    ISSN: 0022-3115

    eISSN: 1873-4820

  149. High heat loading properties of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel

    K. Tokunaga, T. Hotta, K. Araki, Y. Miyamoto, T. Fujiwara, M. Hasegawa, K. Nakamura, K. Ezato, S. Suzuki, M. Enoeda, M. Akiba, T. Nagasaka, R. Kasada, A. Kimura

    JOURNAL OF NUCLEAR MATERIALS 438 S905-S908 2013/07

    DOI: 10.1016/j.jnucmat.2013.01.196  

    ISSN: 0022-3115

    eISSN: 1873-4820

  150. Anisotropic heat transfer characteristics of composite material enhanced with high thermal conductivity fiber

    H. S. Gwon, S. H. Kim, R. Kasada, S. Konishi

    2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 2013

    DOI: 10.1109/SOFE.2013.6635450  

  151. Operation scenario of DT fusion plant without external initial tritium Peer-reviewed

    S. Kwon, R. Kasada, S. Konishi

    2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 2013

    DOI: 10.1109/SOFE.2013.6635449  

  152. Neutronics of sic-lipb high temperature blanket for tritium production

    Saerom Kwon, Satoshi Sato, Ryuta Kasada, Satoshi Konishi

    Fusion Science and Technology 64 (3) 599-603 2013

    Publisher: American Nuclear Society

    DOI: 10.13182/FST12-581  

    ISSN: 1536-1055

  153. Manufacture of vacuum plasma spraying tungsten with homogenous texture on reduced activation ferritic steel at about 873K

    Tomonori Tokunaga, Hideo Watanabe, Naoaki Yoshida, Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura, Masayuki Tokitani, Masatoshi Mitsuhara, Hideharu Nakashima, Suguru Masuzaki, Takeshi Takabatake, Nobuyoshi Kuroki, Koichiro Ezato, Satoshi Suzuki, Masato Akiba

    Plasma and Fusion Research 8 2013

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI: 10.1585/pfr.8.1405111  

    ISSN: 1880-6821

    eISSN: 1880-6821

  154. Enhanced mass transfer of deuterium extracted from falling liquid pb-17li droplets

    Fumito Okino, Kazuyuki Noborio, Ryuta Kasada, Satoshi Konishi

    Fusion Science and Technology 64 (3) 543-548 2013

    Publisher: American Nuclear Society

    DOI: 10.13182/FST12-546  

    ISSN: 1536-1055

  155. 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

  156. Effects of titanium concentration and tungsten addition on the nano-mesoscopic structure of high-Cr oxide dispersion strengthened (ODS) ferritic steels

    Peng Dou, Akihiko Kimura, Ryuta Kasada, Takanari Okuda, Masaki Inoue, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa, Fujio Abe

    Journal of Nuclear Materials 442 (1-3) S95-S100 2013

    DOI: 10.1016/j.jnucmat.2013.04.090  

    ISSN: 0022-3115

  157. A feasibility study of an application of fusion neutron beam source based on cylindrical discharge device for cancer therapy

    Yasunori Nakai, Kazuyuki Noborio, Yuto Takeuchi, Ryuta Kasada, Yasushi Yamamoto, Satoshi Konishi

    Fusion Science and Technology 64 (2) 379-383 2013

    Publisher: American Nuclear Society

    DOI: 10.13182/FST13-A18106  

    ISSN: 1536-1055

  158. Deuterium transport prediction in oscillating liquid pb-17li droplet

    Fumito Okino, Kazuyuki Noborio, Ryuta Kasada, Satoshi Konishi

    Fusion Science and Technology 64 (3) 549-551 2013

    Publisher: American Nuclear Society

    DOI: 10.13182/FST13-A19151  

    ISSN: 1536-1055

  159. Material behavior on heat loading and hydrogen penetration of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel Peer-reviewed

    Kazutoshi Tokunaga, Tomohiro Hotta, Teppei Otsuka, Akira Kobayashi, Kuniaki Araki, Yoshio Miyamoto, Tadashi Fujiwara, Makoto Hasegawa, Kazuo Nakamura, Koichiro Ezato, Satoshi Suzuki, Mikio Enoeda, Masato Akiba, Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura

    Yosetsu Gakkai Ronbunshu/Quarterly Journal of the Japan Welding Society 31 (4) 2013

    DOI: 10.2207/qjjws.31.183s  

    ISSN: 0288-4771

  160. Diffusion bonding between ODS ferritic steel and F82H steel for fusion applications

    Sanghoon Noh, Byungjun Kim, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 426 (1-3) 208-213 2012/07

    DOI: 10.1016/j.jnucmat.2012.02.024  

    ISSN: 0022-3115

  161. Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens

    Byung Jun Kim, Hideaki Mitsui, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 49 (6) 618-631 2012/06

    DOI: 10.1080/00223131.2012.687235  

    ISSN: 0022-3131

  162. Evaluation of grain boundary embrittlement of phosphorus added F82H steel by SSTT

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura, Hiroyasu Tanigawa

    JOURNAL OF NUCLEAR MATERIALS 421 (1-3) 153-159 2012/02

    DOI: 10.1016/j.jnucmat.2011.11.063  

    ISSN: 0022-3115

  163. Validation and evaluation of master Curve method to application for fusion structural materials in fracture toughness

    Kim Byung Jun, Kasada Ryuta, Kimura Akihiko, Wakai Eiichi

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012s 682-682 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012s.0.682.0  

    More details Close

    A new master curve was derived within the framework of the ASTM E1921 standard to apply the master curve method to the F82H steel. A new master curve analysis can be applicable to RAFS to estimate the reference temperature (T0) with proper description of the data scatter in the transition temperature region of fracture toughness than that of the conventional master curve.

  164. A Feasibility study of a medical application of cylindrical discharge type fusion neutron beam source

    NAKAI Yasunori, NOBORIO Kazuyuki, KASADA Ryuta, YAMAMOTO Yasushi, KONISHI Satoshi

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012 756-756 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012f.0.756.0  

  165. Effects of Stress on Irradiation Embrittlement in Reactor Pressure Vessel Steels

    Fujii Katsuhiko, Fukuya Koji, Kasada Ryuta, Kimura Akihiko

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012 407-407 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012f.0.407.0  

  166. Assessment of adoptation of fusion plant into the electricity system

    Konishi Satoshi, Yamamoto Yasushi, Kasada Ryuta

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012 700-700 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012f.0.700.0  

  167. Tritiium mass transfer on oscillating liquid droplet of Pb-17Li

    Okino Fumito, Noborio Kazuyuki, Kasada Ryuuta, Konishi Satoshi

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012 686-686 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012f.0.686.0  

  168. Evaluation of tritium production, breeding behavior in LiPb system

    Kwon Saerom, Noborio Kazuyuki, Kasada Ryuta, Konishi Satoshi

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2012 699-699 2012

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2012f.0.699.0  

  169. The evaluation of thermal conductivity and development of UD-Cf/SiC composite as structural materials for new concept of low temperature gradient divertor Peer-reviewed

    S.H. Kim, Y.J. Lee, T. Hinoki, H.K. Yoo, R. Kasada, S. Konishi

    核融合工学部会夏の学校,青森屋,青森,2012.8.19-22 2012

  170. 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 2011/12

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

    ISSN: 0031-8949

    eISSN: 1402-4896

  171. Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment

    Jerome Isselin, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 48 (12) 1462-1470 2011/12

    DOI: 10.1080/18811248.2011.9711839  

    ISSN: 0022-3131

    eISSN: 1881-1248

  172. Irradiation hardening and microstructure evolution of ion-irradiated Zr-hydride

    Naoko Oono, Ryuta Kasada, Toru Higuchi, Kan Sakamoto, Masafumi Nakatsuka, Akiko Hasegawa, Sosuke Kondo, Hideki Matsui, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 419 (1-3) 366-370 2011/12

    DOI: 10.1016/j.jnucmat.2011.06.041  

    ISSN: 0022-3115

    eISSN: 1873-4820

  173. Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment

    Jerome Isselin, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 48 (12) 1462-1470 2011/12

    DOI: 10.1080/18811248.2011.9711839  

    ISSN: 0022-3131

    eISSN: 1881-1248

  174. Study on Quantitative Evaluation of Fracture Toughness by Small Specimen

    Yusuke UEDA, Yasuhito TAKASHIMA, Mitsuru OHATA, Fumiyoshi MINAMI, Ryuta KASADA, Akihiko KIMURA, Yasuhiro TANIGAWA

    2011/11

  175. Compatibility of SiCf/SiC composite exposed to liquid Pb-Li flow

    C. Park, K. Noborio, R. Kasada, Y. Yamamoto, S. Konishi

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 1218-1220 2011/10

    DOI: 10.1016/j.jnucmat.2011.06.016  

    ISSN: 0022-3115

  176. Effects of specimen size on fracture toughness of phosphorous added F82H steels

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura, Hiroyasu Tanigawa

    FUSION ENGINEERING AND DESIGN 86 (9-11) 2403-2408 2011/10

    DOI: 10.1016/j.fusengdes.2011.04.001  

    ISSN: 0920-3796

  177. Anisotropy in tensile and ductile-brittle transition behavior of ODS ferritic steels

    R. Kasada, S. G. Lee, J. Isselin, J. H. Lee, T. Omura, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 180-184 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.069  

    ISSN: 0022-3115

  178. Microstructures of brazed and solid-state diffusion bonded joints of tungsten with oxide dispersion strengthened steel

    Naoko Oono, Sanghoon Noh, Noriyuki Iwata, Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 253-256 2011/10

    DOI: 10.1016/j.jnucmat.2011.04.004  

    ISSN: 0022-3115

  179. SCC behavior of SUS316L in the high temperature pressurized water environment

    Masahiro Nono, Tetsuya Nakajima, Masahiro Iwama, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 878-882 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.150  

    ISSN: 0022-3115

  180. 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

  181. 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

  182. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

    A. Kimura, R. Kasada, N. Iwata, H. Kishimoto, C. H. Zhang, J. Isselin, P. Dou, J. H. Lee, N. Muthukumar, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, T. F. Abe

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 176-179 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.300  

    ISSN: 0022-3115

  183. Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels

    J. H. Lee, R. Kasada, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 1225-1228 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.279  

    ISSN: 0022-3115

  184. Small specimen test technology and methodology of IFMIF/EVEDA and the further subjects

    E. Wakai, S. Nogami, R. Kasada, A. Kimura, H. Kurishita, M. Saito, Y. Ito, F. Takada, K. Nakamura, J. Molla, P. Garin

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 1325-1330 2011/10

    DOI: 10.1016/j.jnucmat.2011.02.011  

    ISSN: 0022-3115

  185. Microstructure and mechanical properties of friction stir processed ODS ferritic steels

    Sanghoon Noh, Ryuta Kasada, Akihiko Kimura, Seung Hwan C. Park, Satoshi Hirano

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 245-248 2011/10

    DOI: 10.1016/j.jnucmat.2011.01.059  

    ISSN: 0022-3115

  186. Effects of MA environment on the mechanical and microstructural properties of ODS ferritic steels

    Noriyuki Y. Iwata, Tong Liu, Peng Dou, Ryuta Kasada, Akihiko Kimura, Takanari Okuda, Masaki Inoue, Fujio Abe, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 162-165 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.058  

    ISSN: 0022-3115

  187. Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels

    C. H. Zhang, A. Kimura, R. Kasada, J. Jang, H. Kishimoto, Y. T. Yang

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 221-224 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.063  

    ISSN: 0022-3115

  188. Evaluation of fracture behavior of recrystallized and aged high-Cr ODS ferritic steels

    J. Isselin, R. Kasada, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 185-188 2011/10

    DOI: 10.1016/j.jnucmat.2010.12.061  

    ISSN: 0022-3115

  189. Effects of cold work and phosphorous on the ductile to brittle transition behavior of F82H steels

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura, Hiroyasu Tanigawa

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 135-139 2011/10

    DOI: 10.1016/j.jnucmat.2011.01.099  

    ISSN: 0022-3115

  190. Mechanical properties of V-4Cr-4Ti alloy after first-wall coating with tungsten

    Takuya Nagasaka, Takeo Muroga, Hideo Watanabe, Ryuta Kasada, Noriyuki Iwata, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 417 (1-3) 306-309 2011/10

    DOI: 10.1016/j.jnucmat.2011.02.035  

    ISSN: 0022-3115

  191. 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

  192. Solid-state diffusion bonding of high-Cr ODS ferritic steel

    Sanghoon Noh, Ryuta Kasada, Akihiko Kimura

    ACTA MATERIALIA 59 (8) 3196-3204 2011/05

    DOI: 10.1016/j.actamat.2011.01.059  

    ISSN: 1359-6454

  193. Current Status and Issues in Joining Technology of Reduced Activation Ferritic/Martensitic Steel

    HIROSE Takanori, SERIZAWA Hisashi, KISHIMOTO Hirotatsu, OGIWARA Hiroyuki, FUJII Hidetoshi, NAGASAKA Takuya, KASADA Ryuta, NOZAWA Takashi, TANIGAWA Hiroyasu, SHIBA Kiyoyuki

    Journal of plasma and fusion research 87 (3) 172-180 2011/03/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

    More details Close

    ブランケット製作に必要な接合技術開発の現状を紹介する.市販の鉄鋼材料の接合技術を元にブランケット製作に向けて高度化された溶接技術,およびブランケット特有の第一壁形成における固相拡散接合やプラズマ対向材料との異材接合について,接合部特性評価から実規模構造物の製作実証に至る最近の研究開発状況を概説する.

  194. Fusion Neutron Irradiation Effects on Reduced Activation Ferritic/Martensitic Steel

    HAMAGUCHI Dai, KASADA Ryuta, OCHIAI Kentaro, ANDO Masami, TANIGAWA Hiroyasu

    Journal of plasma and fusion research 87 (3) 181-186 2011/03/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

    More details Close

    核融合中性子のスペクトルを忠実に再現する試験照射場が存在しない現状では,核融合中性子照射効果を予測するためには,既存の原子炉やイオン加速器による模擬照射場を最大限利用し,考え得る個々の事象について個別に検証し,得られたデータを複合的に評価しなければならない.また,核融合炉環境で特に問題となり得る,重照射下での強度特性変化を予測するためには,損傷組織発達よりその挙動を機構論的に説明する必要がある.本章では,損傷組織と強度の評価手法に対する考え方,核変換生成物の効果およびその評価手法について概説する.

  195. Current Status and issues on Reduced Activation Ferritic/Martensitic Steel Database

    SHIBA Kiyoyuki, KASADA Ryuta, NOGAMI Shuhei, NAKATA Toshiya, OKUBO Nariaki

    Journal of plasma and fusion research 87 (3) 187-194 2011/03/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

    More details Close

    低放射化フェライト鋼の特性および照射データに関しては,国内においてはF82H鋼を中心にデータが取得されデータベース化されており,基本的な機械的特性,物理特性,熱時効特性など,機器設計に必要なデータは概ね整備されている.また,照射特性についても,HFIR照射やFFTF照射などにより,広い照射温度,照射量にわたる照射データが蓄積されている.また,F82H鋼はIEA低放射化フェライト鋼の共通鋼として,各国の照射プログラム中でも比較材料として照射されており,多くの照射データが得られている.本章ではF82H鋼の各特性データについて紹介するとともに,照射データ取得,特にIFMIF照射の基本要件となっている微小試験片技術開発の成果,機器の長寿命化に必要な耐照射性向上に向けた研究の成果についてまとめた.

  196. Effects of Aluminum on the Corrosion Behavior of 16%Cr ODS Ferritic Steels in a Nitric Acid Solution

    Jerome Isselin, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 48 (2) 169-171 2011/02

    DOI: 10.1080/18811248.2011.9711691  

    ISSN: 0022-3131

    eISSN: 1881-1248

  197. Production of thick high-performance sintered neodymium magnets by grain boundary diffusion treatment with dysprosium-nickel-aluminum alloy

    Naoko Oono, Masato Sagawa, Ryuta Kasada, Hideki Matsui, Akihiko Kimura

    JOURNAL OF MAGNETISM AND MAGNETIC MATERIALS 323 (3-4) 297-300 2011/02

    DOI: 10.1016/j.jmmm.2010.09.021  

    ISSN: 0304-8853

  198. Effects of Aluminum on the Corrosion Behavior of 16%Cr ODS Ferritic Steels in a Nitric Acid Solution

    Jerome Isselin, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 48 (2) 169-171 2011/02

    DOI: 10.1080/18811248.2011.9711691  

    ISSN: 0022-3131

    eISSN: 1881-1248

  199. Preliminary study on nano- and micro-composite sol-gel based alumina coatings on structural components of lead-bismuth eutectic cooled fast breeder reactors

    Peng Dou, Ryuta Kasada

    JOURNAL OF NUCLEAR MATERIALS 409 (3) 177-182 2011/02

    DOI: 10.1016/j.jnucmat.2010.11.022  

    ISSN: 0022-3115

  200. Ion irradiation effect on ultra micro hardness of zirconium hydride

    Higuchi Toru, Kimura Akihiko, Muta Hiroaki, Kimura Hiroaki, Sakamoto Kan, Nakatsuka Masafumi, Kasada Ryuta, Hasegawa Akiko, Kondo Sosuke, Oono Naoko, Hashitomi Okinobu, Matsui Hideki

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2011 (0) 461-461 2011

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2011f.0.461.0  

  201. Positron annihilation lifetime measurements of He-ion-irradiated Fe using pulsed positron beam

    K. Sato, A. Kinomura, T. Omura, Q. Xu, T. Yoshiie, R. Kasada, A. Kimura, K. Morishita

    Journal of Physics: Conference Series 262 2011/01/01

    DOI: 10.1088/1742-6596/262/1/012053  

    ISSN: 1742-6588

  202. Helium ion irradiation effects in ODS and non-ODS ferritic steels

    Ryuta Kasada, Hiromasa Takahashi, Kentaro Yutani, Hirotatsu Kishimoto, Akihiko Kimura

    Green Energy and Technology 66 300-305 2011

    DOI: 10.1007/978-4-431-53910-0_40  

    ISSN: 1865-3529 1865-3537

  203. Specimen size effects on fracture toughness of F82H steel for fusion blanket structural material

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura, Hiroyasu Tanigawa

    Green Energy and Technology 66 286-291 2011

    DOI: 10.1007/978-4-431-53910-0_38  

    ISSN: 1865-3529 1865-3537

  204. Tensile behavior of transient liquid phase bonded ODS ferritic steel joint

    Sanghoon Noh, Ryuta Kasada, Akihiko Kimura

    Green Energy and Technology 66 292-299 2011

    DOI: 10.1007/978-4-431-53910-0_39  

    ISSN: 1865-3529 1865-3537

  205. Recent progress of tungsten R&amp;D for fusion application in Japan

    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

  206. Evaluation of microstructure and mechanical properties of liquid phase diffusion bonded ODS steels

    Sanghoon Noh, Ryuta Kasada, Naoko Oono, Noriyuki Iwata, Akihiko Kimura

    FUSION ENGINEERING AND DESIGN 85 (7-9) 1033-1037 2010/12

    DOI: 10.1016/j.fusengdes.2010.01.001  

    ISSN: 0920-3796

  207. Effects of stress on radiation hardening and microstructural evolution in A533B steel

    K. Fujii, K. Fukuya, R. Kasada, A. Kimura, T. Ohkubo

    JOURNAL OF NUCLEAR MATERIALS 407 (3) 151-156 2010/12

    DOI: 10.1016/j.jnucmat.2010.09.055  

    ISSN: 0022-3115

  208. Corrosion behaviour of 16%Cr-4%Al and 16%Cr ODS ferritic steels under different metallurgical conditions in a supercritical water environment

    J. Isselin, R. Kasada, A. Kimura

    CORROSION SCIENCE 52 (10) 3266-3270 2010/10

    DOI: 10.1016/j.corsci.2010.05.043  

    ISSN: 0010-938X

  209. Evaluation of fracture toughness of F82H steels added with phosphorus by small specimen test technique

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura, Hiroyasu Tanigawa

    International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 3 2001-2007 2010/09/08

  210. Microstructure and mechanical properties of solid state diffusion bonded ODS ferritic steels

    Sanghoon Noh, Ryuta Kasada, Akihiko Kimura

    International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 3 2008-2012 2010/09/07

  211. Study on improvement of heat load characteristic of tungsten coated F82H ferritic/martensitic steel

    Reports of Research Institute for Applied Mechanics,Kyushu University (139) 153-157 2010/09

    Publisher:

    DOI: 10.15017/27101  

    ISSN: 1345-5664

  212. Effects of Zr Addition on the Microstructure of 14% Cr4% Al ODS Ferritic Steels

    Jerome Isselin, Ryuta Kasada, Akihiko Kimura, Takanari Okuda, Masaki Inoue, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa, Fujio Abe

    MATERIALS TRANSACTIONS 51 (5) 1011-1015 2010/05

    DOI: 10.2320/matertrans.MBW200923  

    ISSN: 1345-9678

    eISSN: 1347-5320

  213. Discussion on Mechanism of Stress Corrosion Cracking Resistance of Low-Sigma CSL Grain Boundary

    Wang Yun, Matsui Hideki, Kimura Akihiko, Kasahara Shigeki, Kaneda Junya, Shigenaka Naoto, Hasegawa Akiko, Kondo Sosuke, Hashitomi Okinori, Ohno Naoko, Kasada Ryuta

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2010 (0) 610-610 2010

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2010f.0.610.0  

  214. Effects of Ion-irradiation on Zr-hydrides:(1) hardness change

    Higuchi Toru, Sakamoto Kan, Nakatsuka Masafumi, Kimura Akihiko, Matsui Hideki, Kasada Ryuta, Kondo Sosuke, Oono naoko, hashitomi Okinobu

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2010 (0) 397-397 2010

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2010s.0.397.0  

  215. Effects of Ion-irradiation on Zr-hydrides:(2) microstructure evolution

    OONO Naoko, SAKAMOTO Kan, HIGUCHI Toru, KASADA Ryuta, HASEGAWA Akiko, KONDO Sosuke, HASHITOMI Okinobu, IWATA Noriyuki, MATSUI Hideki, KIMURA Akihiko, NAKATSUKA Masahumi

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2010 (0) 398-398 2010

    Publisher: Atomic Energy Society of Japan

    DOI: 10.11561/aesj.2010s.0.398.0  

  216. Positron annihilation in ODS ferritic alloys Peer-reviewed

    R. Kasada, K. Sato, Q. Xu, S. Noh, T. Yoshiie, A. Kimura

    The Nuclear Materials 2010 (NuMat 2010), ZKM, Karlsruhe, Germany, 2010.10.4-7 2010

  217. Effects of thermal aging on mechanical properties of Fe-Cr ferritic alloys

    R. Kasada, Y. Sakamoto, K. Yabuuchi, A. Kimura, K. Sato, Q. Xu, T. Yoshiie

    KUR Progress report 2010 0-0 2010

  218. Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels

    J. H. Lee, R. Kasada, H. S. Cho, A. Kimura

    ASTM Special Technical Publication 1513 STP 164-175 2010/01/01

    ISSN: 0066-0558

  219. Neutron Irradiation Hardening of Fe-Based Binary Alloys

    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

  220. Microstructural Evaluation of Dy-Ni-Al Grain-Boundary-Diffusion (GBD) Treatment on Sintered Nd-Fe-B Magnet

    Naoko Oono, Masato Sagawa, Ryuta Kasada, Hideki Matsui, Akihiko Kimura

    PRICM 7, PTS 1-3 654-656 2919-+ 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2919  

    ISSN: 0255-5476

  221. Effects of Chemical Composition on the Impact Properties of A533B Steels

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura

    PRICM 7, PTS 1-3 654-656 2895-2898 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2895  

    ISSN: 0255-5476

  222. Microstructure and Tensile Properties of ODS Ferritic Steels Produced by Mechanical Alloying in Argon and Hydrogen Gas Environments

    Noriyuki Y. Iwata, Ryuta Kasada, Akihiko Kimura, Takanari Okuda, Masaki Inoue, Fujio Abe, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa

    PRICM 7, PTS 1-3 654-656 166-+ 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.166  

    ISSN: 0255-5476

  223. Superior Radiation Resistance of ODS Ferritic Steels

    Ryuta Kasada, Hiromasa Takahashi, Hirotatsu Kishimoto, Kentaro Yutani, Akihiko Kimura

    PRICM 7, PTS 1-3 654-656 2791-+ 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2791  

    ISSN: 0255-5476

  224. Joining of ODS steels and Tungsten for Fusion Applications

    Sanghoon Noh, Ryuta Kasada, Naoko Oono, Takuya Nagasaka, Akihiko Kimura

    PRICM 7, PTS 1-3 654-656 2891-+ 2010

    DOI: 10.4028/www.scientific.net/MSF.654-656.2891  

    ISSN: 0255-5476

  225. 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

  226. Development of Small Specimen Technique to Evaluate Ductile-Brittle Transition Behavior of a Welded Reactor Pressure Vessel Steel

    Byung Jun Kim, Ryuta Kasada, Akihiko Kimura

    Green Energy and Technology 44 306-309 2010

    DOI: 10.1007/978-4-431-99779-5_48  

    ISSN: 1865-3529 1865-3537

  227. Relationship Between Microstructure and Mechanical Property of Transient Liquid Phase Bonded ODS Steel

    Sanghoon Noh, Ryuta Kasada, Akihiko Kimura

    Green Energy and Technology 44 339-345 2010

    DOI: 10.1007/978-4-431-99779-5_55  

    ISSN: 1865-3529 1865-3537

  228. Compatibility of materials for advanced blanket with liquid LiPb

    C. Park, K. Noborio, R. Kasada, Y. Yamamoto, G. Nam, S. Konishi

    Proceedings - Symposium on Fusion Engineering 2009/11/10

    DOI: 10.1109/FUSION.2009.5226459  

  229. 施設共用によるエネルギー材料のイノベーション創出に向けた取り組み

    大野 直子, 檜木 達也, 笠田 竜太, 近藤 創介, 松井 秀樹, 木村 晃彦

    まてりあ : 日本金属学会会報 48 (10) 522-522 2009/10/01

    Publisher: The Japan Institute of Metals

    DOI: 10.2320/materia.48.522  

    ISSN: 1340-2625

  230. Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels

    J. H. Lee, R. Kasada, H. S. Cho, A. Kimura

    Journal of ASTM International 6 (8) 2009/09

    DOI: 10.1520/JAI101952  

    ISSN: 1546-962X

  231. THERMOPHYSICAL PROPERTIES AND MICROSTRUCTURE OF PLASMA-SPRAYED TUNGSTEN COATING ON LOW ACTIVATION MATERIALS

    Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura, Yoshio Ueda, Takeo Muroga

    FUSION SCIENCE AND TECHNOLOGY 56 (2) 1053-1057 2009/08

    ISSN: 1536-1055

  232. Statistical evaluation of anisotropic fracture behavior of ODS ferritic steels by using small punch tests

    Naoyuki Okuda, Ryuta Kasada, Akihiko Kimura

    JOURNAL OF NUCLEAR MATERIALS 386-88 974-978 2009/04

    DOI: 10.1016/j.jnucmat.2008.12.265  

    ISSN: 0022-3115

  233. Fusion materials development program in the broader approach activities

    T. Nishitani, H. Tanigawa, S. Jitsukawa, T. Nozawa, K. Hayashi, T. Yamanishi, K. Tsuchiya, A. Moeslang, N. Baluc, A. Pizzuto, E. R. Hodgson, R. Laesser, M. Gasparotto, A. Kohyama, R. Kasada, T. Shikama, H. Takatsu, M. Araki

    JOURNAL OF NUCLEAR MATERIALS 386-88 405-410 2009/04

    DOI: 10.1016/j.jnucmat.2008.12.146  

    ISSN: 0022-3115

    eISSN: 1873-4820

  234. Stability of Y-Ti complex oxides in Fe-16Cr-0.1Ti ODS ferritic steel before and after heavy-ion irradiation

    H. Kishimoto, R. Kasada, O. Hashitomi, A. Kimura

    JOURNAL OF NUCLEAR MATERIALS 386-88 533-536 2009/04

    DOI: 10.1016/j.jnucmat.2008.12.169  

    ISSN: 0022-3115

  235. Effects of helium on ductile-brittle transition behavior of reduced-activation ferritic steels after high-concentration helium implantation at high temperature

    A. Hasegawa, M. Ejiri, S. Nogami, M. Ishiga, R. Kasada, A. Kimura, K. Abe, S. Jitsukawa

    JOURNAL OF NUCLEAR MATERIALS 386-88 241-244 2009/04

    DOI: 10.1016/j.jnucmat.2008.12.102  

    ISSN: 0022-3115

  236. Super ODS steels R&amp;D for fuel cladding of next generation nuclear systems 8) ion irradiation effects at elevated temperatures

    Hirotatsu Kishimoto, Ryuta Kasada, Akihiko Kimura, Masaki Inoue, Takanari Okuda, Fujio Abe, Somei Ohnuki, Toshiharu Fujisawa

    International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 3 2227-2234 2009/01/01

  237. Super ODS steels R&amp;D for fuel cladding of next generation nuclear systems: 6) Corrosion Behavior in SCPW

    J. H. Lee, A. Kimura, R. Kasada, N. Iwata, H. Kishimoto, C. H. Zhang, J. Isselin, P. Dou, N. Muthukumar, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, T. F. Abe

    International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 3 2216-2221 2009/01/01

  238. Super ODS steels R&amp;D for fuel cladding of next generation nuclear systems 5) mechanical properties and microstructure

    R. Kasada, S. G. Lee, J. H. Lee, T. Omura, C. H. Zhang, P. Dou, J. Isselin, A. Kimura, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, T. Okuda, F. Abe

    International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 3 2211-2215 2009/01/01

  239. Super ODS steels R&amp;D for fuel cladding of next generation nuclear systems 1) Introduction and alloy design

    A. Kimura, R. Kasada, N. Iwata, H. Kishimoto, C. H. Zhang, J. Isselin, P. Dou, J. H. Lee, N. Muthukumar, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, T. F. Abe

    International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 3 2187-2194 2009/01/01

  240. Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel

    Noriyuki Y. Iwata, Ryuta Kasada, Akihiko Kimura, Takanari Okuda, Masaki Inoue, Fujio Abe, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa

    ISIJ INTERNATIONAL 49 (12) 1914-1919 2009

    DOI: 10.2355/isijinternational.49.1914  

    ISSN: 0915-1559

  241. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

    H. Tanigawa, T. Hirose, K. Shiba, B. R. Kasada, E. Wakaia, H. Serizawa, Y. Kawahito, S. Jitsukawa, A. Kimura, Y. Kohno, A. Kohyama, S. Katayama, H. Mori, K. Nishimoto, R. L. Klueh, M. A. Sokolov, R. E. Stoller, S. J. Zinkle

    FUSION ENGINEERING AND DESIGN 83 (10-12) 1471-1476 2008/12

    DOI: 10.1016/j.fusengdes.2008.07.024  

    ISSN: 0920-3796

  242. Super ODS steels R&amp;D for cladding of highly efficient nuclear plants

    Akihiko Kimura, Hangsik Cho, Naoki Toda, Ryuta Kasada, Hirotatsu Kishimoto, Noriyuki Iwata, Shigeharu Ukai, Satoshi Ohtsuka, Masayuki Fujiwara

    Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" 4 2148-2154 2008/09/26

  243. High-Cr ODS steels R&D for high burn-up fuel cladding Peer-reviewed

    A. Kimura, H.S. Cho, N. Toda, R. Kasada, K. Yutani, H. Kishimoto, N.Y. Iwata, S. Ukai, M. Fujiwara

    Proceedings of the International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS), Karlsruhe, Germany 103-114 2008/07

    DOI: 10.1787/9789264048072-en  

  244. Effects of MA atmosphere on positron annihilation properties of ODS alloys

    R. Kasada, S.H. Noh, J.H. Lee, A. Kimura, Q. Xu, T.Yoshiie

    KUR Progress report 2008 0-0 2008

  245. Irradiation hardening and microstructure evolution of ion-irradiated ODS ferritic steels

    Kentaro Yutani, Ryuta Kasada, Hirotatsu Kishimoto, Akihiko Kimura

    ASTM Special Technical Publication 1492 STP 149-156 2008/01/01

    ISSN: 0066-0558

  246. Effects of neutron irradiation and thermal aging on mechanical properties of ODS ferritic steels for advanced nuclear systems

    Ryuta Kasada, Hang Sik Cho, Naoyuki Okuda, Akihiko Kimura

    Materials Science Forum 561-565 1773-1776 2007/12/01

    ISSN: 0255-5476

  247. Impact of N-isotope composition control of ferritic steel on classification of radioactive materials from fusion reactor

    T. Hayashi, R. Kasada, K. Tobita, S. Nishio, T. Sawai, H. Tanigawa, S. Jitsukawa

    FUSION ENGINEERING AND DESIGN 82 (15-24) 2850-2855 2007/10

    DOI: 10.1016/j.fusengdes.2007.01.007  

    ISSN: 0920-3796

  248. Recent progress in US-Japan collaborative research on ferritic steels R&D

    Akihiko Kimura, Ryuta Kasada, Akira Kohyama, Hiroyasu Tanigawa, Takanori Hirose, Kiyoyuki Shiba, Shiro Jitsukawa, Satoshi Ohtsuka, Shigeharu Ukai, M. A. Sokolov, R. L. Klueh, Takuya Yamamoto, G. R. Odette

    JOURNAL OF NUCLEAR MATERIALS 367 60-67 2007/08

    DOI: 10.1016/j.jnucmat.2007.03.013  

    ISSN: 0022-3115

  249. Pre- and post-deformation microstructures of oxide dispersion strengthened ferritic steels

    R. Kasada, N. Toda, K. Yutani, H. S. Cho, H. Kishimoto, A. Kimura

    JOURNAL OF NUCLEAR MATERIALS 367 222-228 2007/08

    DOI: 10.1016/j.jnucmat.2007.03.141  

    ISSN: 0022-3115

  250. Effects of neutron irradiation on the tensile properties of high-Cr oxide dispersion strengthened ferritic steels

    H. S. Cho, R. Kasada, A. Kimura

    JOURNAL OF NUCLEAR MATERIALS 367 239-243 2007/08

    DOI: 10.1016/j.jnuemat.2007.03.140  

    ISSN: 0022-3115

  251. Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

    K. Yutani, H. Kishimoto, R. Kasada, A. Kimura

    JOURNAL OF NUCLEAR MATERIALS 367 423-427 2007/08

    DOI: 10.1016/j.jnucmat.2007.03.016  

    ISSN: 0022-3115

  252. Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels

    H. Kishimoto, K. Yutani, R. Kasada, O. Hashitomi, A. Kimura

    JOURNAL OF NUCLEAR MATERIALS 367 179-184 2007/08

    DOI: 10.1016/j.jnucmat.2007.03.149  

    ISSN: 0022-3115

  253. Irradiation hardening and microstructure evolution of ion-irradiated ODS ferritic steels Peer-reviewed

    Kentaro Yutani, Ryuta Kasada, Hirotatsu Kishimoto, Akihiko Kimura

    Journal of ASTM International 4 (7) 2007/07

    DOI: 10.1520/JAI100701  

    ISSN: 1546-962X

  254. Irradiation hardening and microstructure evolution of ion-irradiated ODS ferritic steels

    Kentaro Yutani, Ryuta Kasada, Hirotatsu Kishimoto, Akihiko Kimura

    Journal of ASTM International 4 2007/07/01

    DOI: 10.1520/JAI100701  

  255. High burnup fuel cladding materials R&D for advanced nuclear systems - Nano-sized oxide dispersion strengthening steels

    Akihiko Kimura, Han-Sik Cho, Naoki Toda, Ryuta Kasada, Kentaro Yutani, Hirotatsu Kishimoto, Noriyuki Iwata, Shigeharu Ukai, Masayuki Fujiwara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 44 (3) 323-328 2007/03

    DOI: 10.1080/18811248.2007.9711289  

    ISSN: 0022-3131

    eISSN: 1881-1248

  256. Fuel cladding materials R&amp;D for high burn-up operation of advanced nuclear energy systems

    Akihiko Kimura, Hangsik Cho, Naoki Toda, Ryuta Kasada, Hirotatsu Kishimoto, Noriyuki Iwata, Shigeharu Ukai, Satoshi Ohtsuka, Masayuki Fujiwara

    Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06 2006 2229-2237 2006/12/01

  257. Helium cavity formation research on oxide dispersed strengthening (ODS) ferritic steels utilizing dual-ion irradiation facility

    H Kishimoto, K Yutani, R Kasada, A Kimura

    FUSION ENGINEERING AND DESIGN 81 (8-14) 1045-1049 2006/02

    DOI: 10.1016/j.fusengdes.2005.09.049  

    ISSN: 0920-3796

  258. Small specimen test technique for evaluating fracture toughness of blanket structural materials

    R Kasada, H Ono, A Kimura

    FUSION ENGINEERING AND DESIGN 81 (8-14) 981-986 2006/02

    DOI: 10.1016/j.fusengdes.2005.08.088  

    ISSN: 0920-3796

  259. Ferritic steel-blanket systems integration R&D - Compatibility assessment

    A Kimura, R Kasada, A Kohyama, S Konishi, M Enoeda, M Akiba, S Jitsukawa, S Ukai, Terai, I, A Sagara

    FUSION ENGINEERING AND DESIGN 81 (8-14) 909-916 2006/02

    DOI: 10.1016/j.fusengdes.2005.09.018  

    ISSN: 0920-3796

  260. 国際核融合材料照射施設(IFMIF)の設計と開発の現状 2.テストセル系の開発 Peer-reviewed

    清水昭比古, 木村晃彦, 笠田竜太, 栗下裕明, 馬場護

    プラズマ・核融合学会誌 82 (1) 7-15 2006/01/25

  261. Effects of alloying elements on irradiation hardening of Fe-Mn model alloys Peer-reviewed

    R. Kasada, K. Yabuuchi, A. Kimura, Q. Xu, T. Yoshiie

    KURRI Progress Report 114- 2006

  262. Effects of neutron dose, dose rate, and irradiation temperature on the irradiation embrittlement of a low-copper reactor pressure vessel steel

    Ryuta Kasada, Takeshi Kudo, Akihiko Kimura, Hideki Matsui, Minoru Narui

    ASTM Special Technical Publication 1475 STP 225-235 2006/01/01

    ISSN: 0066-0558

  263. Assessment of neutron irradiation-induced grain boundary embrittlement by phosphorous segregation in a reactor pressure vessel steel

    Akihiko Kimura, Masaaki Shibata, Ryuta Kasada, Katsuhiko Fujii, Kohji Fukuya, Hayato Nakata

    ASTM Special Technical Publication 1475 STP 212-224 2006/01/01

    ISSN: 0066-0558

  264. Grain boundary phosphorus segregation in thermally aged low alloy steels

    Hayato Nakata, Katsuhiko Fujii, Koji Fukuya, Ryuta Kasada, Akihiko Kimura

    Journal of Nuclear Science and Technology 43 (7) 785-793 2006

    DOI: 10.3327/jnst.43.785  

    ISSN: 0022-3131

  265. Grain boundary phosphorus segregation in thermally aged low alloy steels

    Hayato Nakata, Katsuhiko Fujii, Koji Fukuya, Ryuta Kasada, Akihiko Kimura

    Journal of Nuclear Science and Technology 43 (7) 785-793 2006

    DOI: 10.3327/jnst.43.785  

    ISSN: 0022-3131

  266. Fuel cladding materials R&amp;D for high burn-up operation of advanced water-cooling nuclear energy systems

    Akihiko Kimura, Hangsik Cho, Naoki Toda, Ryuta Kasada, Hirotatsu Kishimoto, Noriyuki Iwata, Shigeharu Ukai, Masayuki Fujiwara

    Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 3 1737-1745 2005/12/01

  267. Tensile deformation behavior of oxide-dispersion strengthened ferritic steels

    R. Kasada, N. Toda, H. S. Cho, A. Kimura

    Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 3 1703-1711 2005/12/01

  268. Microstructural evolution by heavy damage accumulation on high chromium oxide dispersion strengthening (ODS) ferritic steels

    H. Kishimoto, K. Yutani, R. Kasada, R. Kasada, A. Kimura, A. Kimura

    Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 4 2432-2439 2005/12/01

  269. Recent progress in fuel cladding materials R&D for high burn-up operation of advanced water-cooling nuclear energy systems

    A. Kimura, H. Cho, N. Toda, R. Kasada, H. Kishimoto, N. Iwata, S. Ukai, M. Fujiwara

    Proceedings of the 2005 Water Reactor Fuel Performance Meeting (WRFPM 2005), Kyoto, Japan 170-177 2005/10

  270. Effects of neutron dose, dose rate, and irradiation temperature on the irradiation embrittlement of a low-copper reactor pressure vessel steel

    Ryuta Kasada, Takeshi Kudo, Akihiko Kimura, Hideki Matsui, Minoru Narui

    Journal of ASTM International 2 (3) 213-223 2005/03/01

  271. Effects of nickel addition on microstructural evolution and mechanical properties of reduced activation martensitic steels irradiated in the ATR-A1

    R Kasada, A Kimura

    MATERIALS TRANSACTIONS 46 (3) 475-480 2005/03

    DOI: 10.2320/matertrans.46.475  

    ISSN: 1345-9678

    eISSN: 1347-5320

  272. Assessment of neutron irradiation-induced grain boundary embrittlement by phosphorous segregation in a reactor pressure vessel steel

    Akihiko Kimura, Masaaki Shibata, Ryuta Kasada, Katsuhiko Fujii, Kohji Fukuya, Hayato Nakata

    Journal of ASTM International 2 (3) 199-211 2005/03

    DOI: 10.1520/JAI12398  

  273. R &amp; D of oxide dispersion strengthening steels for high burn-up fuel claddings

    A. Kimura, H. S. Cho, J. S. Lee, R. Kasada, S. Ukai, M. Fujiwara

    Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04 2070-2076 2004/12/01

  274. Specimen size effects on fracture toughness of JLF-1 reduced-activation ferritic steel

    H Ono, R Kasada, A Kimura

    JOURNAL OF NUCLEAR MATERIALS 329 1117-1121 2004/08

    DOI: 10.1016/j.jnucmat.2004.04.034  

    ISSN: 0022-3115

  275. Microstructural characteristics and embrittlement phenomena in neutron irradiated 309L stainless steel RPV clad

    JS Lee, IS Kim, R Kasada, A Kimura

    JOURNAL OF NUCLEAR MATERIALS 326 (1) 38-46 2004/03

    DOI: 10.1016/j.jnucmat.2003.11.005  

    ISSN: 0022-3115

  276. Grain boundary phosphorous segregation and its influence on the ductile brittle transition temperature in reactor pressure vessel steels Peer-reviewed

    A Kimura, M Shibata, R Kasada, H Nakata, K Fujii, K Fukuya

    EFFECTS OF RADIATION ON MATERIALS: 21ST INTERNATIONAL SYMPOSIUM 1447 565-578 2004

    ISSN: 1040-1695

  277. Irradiation hardening and microstructural evolution in Fe-Cu model alloys Peer-reviewed

    T Kitao, R Kasada, A Kimura, H Nakata, K Fukuya, H Matsui, M Narui

    Effects of Radiation on Materials: 21st International Symposium 1447 365-375 2004

    ISSN: 1040-1695

  278. Irradiation hardening of Fe-based model alloys irradiated in the URRI-LINAC with temperature-controlling Equipments Peer-reviewed

    R. Kasada, M. Saito, N. Toda, A. Kimura, T. Yoshiie

    KURRI Progress Report 47- 2004

  279. Grain boundary phosphorous segregation and its influence on the ductile brittle transition temperature in reactor pressure vessel steels

    A. Kimura, M. Shibata, R. Kasada, H. Nakata, K. Fujii, K. Fukuya

    ASTM Special Technical Publication (1447) 565-578 2004/01/01

    ISSN: 0066-0558

  280. Irradiation hardening and microstructaral evolution in Fe-Cu model aloys

    Takeshi Kitao, Ryuta Kasada, Akihiko Kimura, Hayato Nakata, Kouji Fukuya, Hideki Matsui, Minoru Narui

    ASTM Special Technical Publication (1447) 365-375 2004/01/01

    ISSN: 0066-0558

  281. Factors Controlling Irradiation Hardening of Iron-Copper Model Alloy

    Takeshi Kudo, Ryuta Kasada, Akihiko Kimura, Kazuhiro Hono, Kouji Fukuya, Hideki Matsui

    Materials Transactions 45 (2) 338-341 2004

    Publisher: Japan Institute of Metals (JIM)

    DOI: 10.2320/matertrans.45.338  

    ISSN: 1345-9678

  282. Influence of neutron irradiation on hardening and embrittlement phenomena in reactor pressure vessel cladding material

    J. S. Lee, I. S. Kim, R. Kasada, A. Kimura

    Materials Science Forum 426-432 4477-4482 2003/07/21

    ISSN: 0255-5476

  283. 高効率・環境調和型超高温ガス冷却高速炉 Peer-reviewed

    香山晃, 朴峻秀, 野澤貴史, 原田敏夫, 石川敏弘, 田中吉積, 佐藤光彦, 宮本典史, 伊藤正彦, 鵜飼重治, 水野朋保, 功刀資彰, 佐竹信一, 横峰健彦, 木村晃彦, 森下和功, 神保光一, 笠田竜太

    炉心構造体の先進材料システム開発,成果報告書,2003 2003

  284. HFIR照射した低放射化フェライト鋼・ODS鋼の強度特性 Peer-reviewed

    笠田竜太, 木村晃彦, 鵜飼重治, R.L. Klueh, S.J. Zinkle

    日本原子力学会2003年春の年会,2003 2003

  285. Development of the electron-irradiation system with temperature-controlling equipments for the KURRI-LINAC Peer-reviewed

    R. Kasada, T. Kudo, M. Salto, N. Toda, A. Kimura, T. Yoshiie

    KURRI Progress Report 79- 2003

  286. Mechanical properties of JLF-1 reduced-activation ferritic steels

    Kasada, R., Ono, H., Sakasegawa, H., Hirose, T., Kimura, A., Kohyama, A.

    Fusion Science and Technology 44 (1) 145-149 2003

    DOI: 10.13182/FST03-A324  

    ISSN: 1536-1055

  287. High resistance to helium embrittlement in reduced activation martensitic steels

    A Kimura, R Kasada, K Morishita, R Sugano, A Hasegawa, K Abe, T Yamamoto, H Matsui, N Yoshida, BD Wirth, TD Rubia

    JOURNAL OF NUCLEAR MATERIALS 307 521-526 2002/12

    DOI: 10.1016/S0022-3115(02)01211-4  

    ISSN: 0022-3115

  288. Effect of helium implantation on mechanical properties and microstructure evolution of reduced-activation 9Cr-2W martensitic steel

    R Kasada, T Morimura, A Hasegawa, A Kimura

    JOURNAL OF NUCLEAR MATERIALS 299 (1) 83-89 2001/10

    DOI: 10.1016/S0022-3115(01)00660-2  

    ISSN: 0022-3115

  289. Relation between resistivity and mechanical properties in heat affected zone of welded pressure vessel steel Peer-reviewed

    R Kasada, T Suzuki, K Itoh, Y Naruse, A Kimura

    EFFECTS OF RADIATION ON MATERIALS: 20TH INTERNATIONAL SYMPOSIUM 1045 315-327 2001

    ISSN: 1040-1695

  290. Effects of copper concentration and neutron flux on irradiation hardening and microstructure evolution in Fe-Cu model alloys Peer-reviewed

    R Kasada, T Kitao, K Morishita, H Matsui, A Kimura

    EFFECTS OF RADIATION ON MATERIALS: 20TH INTERNATIONAL SYMPOSIUM 1045 237-246 2001

    ISSN: 1040-1695

  291. Dependence of susceptibility to IGSCC on the location in HAZ of welded SUS304L core shroud for BWR Peer-reviewed

    K Isomura, A Kimura, R Kasada, K Itoh, H Yuya, Y Naruse

    PRICM 4: FORTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, VOLS I AND II 1443-1446 2001

  292. Effects of copper concentration and neutron flux on irradiation hardening and microstructure evolution in Fe-Cu model alloys

    Ryuta Kasada, Takeshi Kitao, Kazunori Morishita, Hideki Matsui, Akihiko Kimura

    Institution of Chemical Engineers Symposium Series (148) 237-246 2000/12/01

    ISSN: 0307-0492

  293. Relation between resistivity and mechanical properties in heat affected zone of welded pressure vessel steel

    Ryuta Kasada, Tetsuya Suzuki, Keisuke Itoh, Yoshinobu Naruse, Akihiko Kimura

    Institution of Chemical Engineers Symposium Series (148) 315-327 2000/12/01

    ISSN: 0307-0492

  294. Evaluation of ductile-brittle transition behavior of helium-implanted reduced activation 9Cr-2W martensitic steel by small punch tests

    Akihiko Kimura, Taro Morimura, Ryuta Kasada, Hideki Matsui, Akira Hasegawa, Katsunori Abe

    ASTM Special Technical Publication (1366) 626-641 2000/12/01

    ISSN: 1040-3094

  295. Two-step recovery process of irradiation hardening in 1%Ni doped 9%Cr-2%W martensitic steel

    Ryuta Kasada, Taro Morimura, Hideki Matsui, Minoru Narui, Akihiko Kimura

    ASTM Special Technical Publication (1366) 448-459 2000/12/01

    ISSN: 1040-3094

  296. Modeling of microstructure evolution and mechanical property change of reduced-activation martensitic steel during varying-temperature irradiation

    R Kasada, A Kimura

    JOURNAL OF NUCLEAR MATERIALS 283 188-192 2000/12

    DOI: 10.1016/S0022-3115(00)00306-8  

    ISSN: 0022-3115

  297. Annealing behavior of irradiation hardening and microstructure in helium-implanted reduced activation martensitic steel

    A Kimura, R Kasada, R Sugano, A Hasegawa, H Matsui

    JOURNAL OF NUCLEAR MATERIALS 283 827-831 2000/12

    DOI: 10.1016/S0022-3115(00)00090-8  

    ISSN: 0022-3115

  298. Two-step recovery process of irradiation hardening in 1%Ni doped 9%Cr-2%W martensitic steel Peer-reviewed

    R Kasada, T Morimura, H Matsui, M Narui, A Kimura

    EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM 1366 448-459 2000

    ISSN: 1040-1695

  299. Evaluation of ductile-brittle transition behavior of helium-implanted reduced activation 9Cr-2W martensitic steel by small punch tests Peer-reviewed

    A Kimura, T Morimura, R Kasada, H Matsui, A Hasegawa, K Abe

    EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM 1366 626-641 2000

    ISSN: 1040-1695

  300. Effects of varying temperature irradiation on the neutron irradiation hardening of reduced-activation 9Cr-2W martensitic steels

    R Kasada, A Kimura, H Matsui, M Hasegawa, M Narui

    JOURNAL OF NUCLEAR MATERIALS 271 360-364 1999/05

    DOI: 10.1016/S0022-3115(98)00749-1  

    ISSN: 0022-3115

  301. Enhancement of irradiation hardening by nickel addition in the reduced-activation 9Cr-2W martensitic steel

    R. Kasada, A. Kimura, H. Matsui, M. Narui

    Journal of Nuclear Materials 258-263 1199-1203 1998

    Publisher: Elsevier

    DOI: 10.1016/S0022-3115(98)00186-X  

    ISSN: 0022-3115

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    日本金属学会講演大会(Web) 176th 2025

  4. 低活性高Mn酸化物分散強化アルミナ生成オーステナイト系鋼の室温および高温における機械的特性

    耿殿程, YU Hao, 長谷川晃, 荻野靖之, 近藤創介, 宮澤順一, 笠田竜太

    日本金属学会講演大会(Web) 176th 2025

  5. メソスケールヘテロ組織を有する鉄基ODS合金の強度特性および変形挙動

    小川和希, 小川和希, 耿殿程, 余浩, 荻野靖之, PARK Minha, 近藤創介, 笠田竜太

    日本金属学会講演大会(Web) 176th 2025

  6. Effect of Y2O3/Hf contents on the oxidation behavior and mechanical properties of Co10Ni20Cr15Al ODS superalloys

    余浩, 近藤創介, 荻野靖之, PARK Minha, 笠田竜太

    日本金属学会講演大会(Web) 176th 2025

  7. 強度特性と熱伝導特性のトレードオフ克服を目指したガスアトマイズCuYZr-WO3酸化物分散強化銅合金の機械特性および微細組織

    高子墨, 高子墨, 耿殿程, 余浩, 笠田竜太, 近藤創介, 荻野靖之, 井上耕治

    日本金属学会講演大会(Web) 176th 2025

  8. The influence of MA element addition process on the oxide particle dispersion in ODS-Cu

    齋藤隼輝, YU Hao, GAO Zimo, 陣場優貴, 荻野靖之, 井上耕治, 近藤創介, 笠田竜太

    日本原子力学会春の年会予稿集(CD-ROM) 2025 2025

  9. Investigation of local mechanical properties and microstructure of under-clad hardened layer of RPV steel

    遠藤美奈子, 遠藤美奈子, 笠田竜太, 陣場優貴, GENG Diancheng, 上山魁, PARK Minha, 荻野靖之, YU Hao, 近藤創介, 熊野秀樹

    日本原子力学会春の年会予稿集(CD-ROM) 2025 2025

  10. 鉄クロム二元合金の100°C温度領域における中性子照射硬化挙動

    上山魁, 外山健, 井上耕治, 永井康介, 佐藤紘一, 耿殿程, 荻野靖之, 余浩, 近藤創介, 笠田竜太

    日本金属学会講演大会(Web) 175th 2024

  11. Corrosion Behavior of Additive Manufactured SiC in high temperature and high pressure water.

    岡田航汰, 岡田航汰, 近藤創介, 宮岸太一, 宮岸太一, YU Hao, 荻野靖之, 笠田竜太

    日本セラミックス協会年会講演予稿集(Web) 2024 2024

  12. Development of radiation sensing technology based on solar cell

    奥野泰希, 奥野泰希, 小林知洋, 大竹淑恵, 今泉充, 上川由紀子, 岡本保, 栗本裕司, 陣場優貴, 荻野靖之, 笠田竜太, 中村徹哉

    応用物理学会秋季学術講演会講演予稿集(CD-ROM) 85th 2024

    ISSN: 2758-4704

  13. ナノインデンテーションを用いたFe2M Laves相の機械的特性評価

    板垣克, 板垣克, 耿殿程, 耿殿程, 陣場優貴, 余浩, 荻野靖之, 近藤創介, 笠田竜太

    日本金属学会講演大会(Web) 175th 2024

  14. Development of the sintered metal boride as the advanced radiation shielding materials

    荻野靖之, 陣場優貴, 板垣克, YU Hao, 近藤創介, 笠田竜太

    東北大学金属材料研究所新素材共同研究開発センター共同利用研究報告書(CD-ROM) 2023 2024

  15. Overcoming the Trade-off Relationship between Strength and Thermal Conductivity in ODS-Cu for Divertor and Elucidating the Mechanism

    YU Hao, 笠田竜太, 近藤創介, 荻野靖之, WU Xiangyu, GENG Diancheng, 齋藤隼輝, YUAN Xinwei, 板垣克, 山村海爾

    東北大学金属材料研究所新素材共同研究開発センター共同利用研究報告書(CD-ROM) 2023 2024

  16. Effect of CVD temperature on the strength of thin ceramic films

    近藤創介, 岩本空, 且井宏和, 宮岸太一, YU Hao, 荻野靖之, 笠田竜太

    日本セラミックス協会年会講演予稿集(Web) 2024 2024

  17. Analysis of the Phenomenon of Increased Interfacial Strength after Irradiation in Double-Layer Ceramic Coatings on Silicon Carbide

    宮岸太一, 近藤創介, 荻野靖之, YU Hao, 笠田竜太

    日本セラミックス協会秋季シンポジウム講演予稿集(Web) 37th 2024

  18. Development of Tungsten Boride Cermet for Radiation Shielding Material in Fusion Reactor

    山村海爾, 荻野靖之, 陣場優貴, YU Hao, 近藤創介, 笠田竜太

    日本原子力学会秋の大会予稿集(CD-ROM) 2024 2024

  19. Suppression of irradiation hardening in W-coated F82H produced by underwater explosive-welding

    関航太朗, 外本和幸, 田中茂, 小柳孝彰, 吉田健太, 長谷川晃, 近藤創介, YU Hao, 荻野靖之, 笠田竜太, 笠田竜太

    日本原子力学会秋の大会予稿集(CD-ROM) 2024 2024

  20. Study on the local mechanical properties at the interface of RPV cladding

    野呂崇史, 笠田竜太, YU Hao, GENG Diancheng, 近藤創介, 熊野秀樹, 遠藤美奈子

    日本原子力学会春の年会予稿集(CD-ROM) 2023 2023

  21. Fe2M Laves相の機械的特性

    板垣克, 板垣克, 笠田竜太, 近藤創介, 耿殿程, 耿殿程, 余浩, 陣場優貴, 陣場優貴

    日本金属学会講演大会(Web) 173rd 2023

  22. Cr23C6およびCr23B1C5の機械的性質および変形挙動に及ぼす照射の影響

    松戸玲菜, 松戸玲菜, 水元希, 水元希, 耿殿程, 耿殿程, 余浩, 近藤創介, 笠田竜太

    日本金属学会講演大会(Web) 173rd 2023

  23. 低放射化フェライト鋼の押込み硬さの統計的性質に及ぼすサイズ効果

    古川雄磨, 古川雄磨, GENG Diancheng, GENG Diancheng, 近藤創介, 余浩, 荻野靖之, 笠田竜太

    日本金属学会講演大会(Web) 173rd 2023

  24. Effect of irradiation on the fracture performance and adhesion strength of alumina scales formed on FeCrAl ferritic ODS alloys

    余浩, 近藤創介, 荻野靖之, 笠田竜太

    日本金属学会講演大会(Web) 173rd 2023

  25. Production and evaluation of high melting-point borides towards nuclear application (1) Creation and evaluation of a tungsten-boron shielding material optimized by radiation transport code

    荻野靖之, 山村海爾, 陣場優貴, YU Hao, 近藤創介, 笠田竜太

    日本原子力学会秋の大会予稿集(CD-ROM) 2023 2023

  26. Production and evaluation of high melting-point borides towards nuclear application (2) Evaluation of applicability of Si impregnation method to improve oxidation resistance of high melting point borides

    若旅航基, 笠田竜太, 陣場優貴, YU Hao, 近藤創介

    日本原子力学会秋の大会予稿集(CD-ROM) 2023 2023

  27. Development of Al-added high-Mn austenite ODS steels for advanced fusion reactors

    笠田竜太, GENG Diancheng, YU Hao, 近藤創介, 荻野靖之, 宮澤順一

    プラズマ・核融合学会年会(Web) 40th 2023

  28. Evaluation of hardness change of W/F82H after neutron irradiation

    関航太朗, 外本和幸, 田中茂, 吉田健太, 宮田穂高, 長谷川晃, 近藤創介, YU Hao, 荻野靖之, WU Xiangyu, 笠田竜太

    プラズマ・核融合学会年会(Web) 40th 2023

  29. Production and evaluation of high melting-point borides towards nuclear application (3) Effects of ball-milled Ti additives on low-temperature densification of TiB2

    陣場優貴, 奥野泰希, 荻野靖之, YU Hao, 近藤創介, 笠田竜太

    日本原子力学会秋の大会予稿集(CD-ROM) 2023 2023

  30. Investigation of anti-corrosion effect by hydrogen termination of SiC unpaired bonds on irradiation resistance

    近藤創介, 関航太朗, LYU Shaofan, 岩本空, YUAN Xinwei, YU Hao, 奥野泰希, 笠田竜太

    東北大学金属材料研究所新素材共同研究開発センター共同利用研究報告書(CD-ROM) 2022 2023

  31. Estimation of Radiation Tolerance of CIGS Solar Cell Dosimeters by Applying the Displacement Damage Dose Method of Radiation Degradation Prediction Model for Space Solar Cell

    奥野泰希, 上川由紀子, 今泉充, 牧野高紘, 佐藤信浩, 陣場優貴, 笠田竜太

    応用物理学会秋季学術講演会講演予稿集(CD-ROM) 84th 2023

    ISSN: 2758-4704

  32. Establishment of a method to reduce unpaired electron density of SiC and verification of its effect on corrosion resistance

    関航太朗, 近藤創介, 笠田竜太, 佐藤紘一

    日本セラミックス協会秋季シンポジウム講演予稿集(Web) 35th 2022

  33. Development of Miniature Evaluation Techniques for Interfacial Strength of Multilayer Ceramic Coatings

    近藤創介, LYU Shaofan, 且井宏和, YU Hao, 笠田竜太

    日本セラミックス協会秋季シンポジウム講演予稿集(Web) 35th 2022

  34. Development of Ring-on-ring testing method for evaluating the strength of thin ceramic films

    岩本空, 近藤創介, 且井宏和, 薄川隆太郎, LYU Shaofan, 笠田竜太

    日本セラミックス協会秋季シンポジウム講演予稿集(Web) 35th 2022

  35. Combined effects of Ti-B eutectic aid on sintering temperature and strength of TiB2

    陣場優貴, 近藤創介, YU H., 奥野泰希, 笠田竜太

    日本セラミックス協会秋季シンポジウム講演予稿集(Web) 35th 2022

  36. Formation of fine YSZ particles in Zr-added ODS-Cu

    齋藤隼輝, YU Hao, 井上耕治, GAO Zimo, 近藤創介, 笠田竜太, 永井康介

    日本金属学会東北支部研究発表大会予稿集 21st (Web) 2022

  37. Microstructure changes of SiC fiber due to impurities induced internal oxidation

    袁欣偉, 袁欣偉, 近藤創介, 下田一哉, 余浩, 奥野泰希, 笠田竜太

    日本金属学会講演大会(Web) 170th 2022

  38. Development of Multiple Corrosion Protection Technology for SiC

    近藤創介, 関航太朗, LYU Shaofan, 岩本空, 笠田竜太, 且井宏和, 下田一哉

    日本セラミックス協会秋季シンポジウム講演予稿集(Web) 34th 2021

  39. SiC表面へのムライト/アルミナ連続CVD被膜形成による防食効果

    近藤創介, 且井宏和, LYU Shaofan, 下田一哉, 余浩, 奥野泰樹, 笠田竜太

    日本金属学会講演大会(Web) 168th 2021

  40. Passive oxidation and related mechanical properties of SiC fibers

    袁欣偉, 近藤創介, 下田一哉, 余浩, 奥野泰希, 笠田竜太

    日本金属学会講演大会(Web) 168th 2021

  41. The comparison of oxidation rate and compressive strength between two SiC fibers

    袁欣偉, 袁欣偉, 近藤創介, 下田一哉, 余浩, 奥野泰希, 笠田竜太

    日本金属学会講演大会(Web) 169th 2021

  42. Chemical compatibility of ODS FeCrAl alloys for liquid Sn divertor concepts

    宮川幸大, 近藤正聡, 大野直子, 笠田竜太, HAO Yu, 坂本寛, 田中照也

    日本原子力学会秋の大会予稿集(CD-ROM) 2021 2021

  43. Neutron flux detection using InGaP solar cell covered over boron converter

    奥野泰希, 今泉充, 小林知洋, 岡本保, 秋吉優史, 後藤康仁, 牧野高紘, 大島武, 近藤創介, YU Hao, 笠田竜太

    応用物理学会春季学術講演会講演予稿集(CD-ROM) 68th 2021

  44. Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts (6) Development of Al-added high-Mn ODS austenitic steel for liquid metal environment

    笠田竜太, WANG Haoran, LIU Jiarui, YU Hao, 近藤創介, 奥野泰希, 大久保成彰, 徳永透子, 大野直子

    日本原子力学会春の年会予稿集(CD-ROM) 2021 2021

  45. Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts (4) Experimental study on chemical compatibility for the development of fusion reactor components

    近藤正聡, 宮澤順一, 田中照也, 大野直子, 秋吉優史, 坂本寛, 植木祥高, 菱沼良光, 笠田竜太, 波多野雄治, PINT Bruce, JIHEON Jun, RUSSEL Nick

    日本原子力学会春の年会予稿集(CD-ROM) 2021 2021

  46. Saloon : Student Perspective on COVID-19 Related Life Changes : Report of On-Line Seminars on Nuclear Fusion Reactors Organized by Young Generation Informal Group of Nuclear Fusion Research

    Journal of plasma and fusion research 96 (9) 519-521 2020/09

  47. サロン:アウトリーチヘッドクォーターの設置にあたって

    小川 雄一, 笠田 竜太, 吉澤 菜穂美, 東島 智, 矢治 健太郎

    プラズマ・核融合学会誌 96 (5) 269-272 2020/05

  48. Study on relationship between lattice defects and corrosion of irradiated SiC

    近藤創介, YU Hao, 笠田竜太, 深見一弘, 前田有輝

    東北大学金属材料研究所新素材共同研究開発センター共同利用研究報告書(CD-ROM) 2019 2020

  49. 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

  50. 材料の硬さの科学技術コミュニケーション

    笠田竜太

    材料試験技術 65 (1) 62-64 2020/01

  51. 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

  52. Development of Oxide Dispersion Strengthened (ODS) Copper for the Divertor of Nuclear Fusion Reactors

    95 (8) 370-373 2019/08

    Publisher: プラズマ・核融合学会編集委員会

    ISSN: 0918-7928

  53. 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

  54. Study on the hydrothermal corrosion of irradiated SiC

    近藤創介, 松川義孝, YU Hao, 笠田竜太, 深見一弘, 前田有輝

    東北大学金属材料研究所新素材共同研究開発センター共同利用研究報告書(CD-ROM) 2018 2019

  55. REDOX反応制御MA法によるODS-Cu合金の創製

    笠田竜太, 八尾栄彰, 小西哲之, AGHAMIRI Mohammad, 大野直子, 鵜飼重治, 能登裕之, 菱沼良光, 室賀健夫

    日本原子力学会春の年会予稿集(CD-ROM) 2018 2018

  56. SiCの高温高圧水腐食への照射欠陥の影響

    近藤創介, 深見一弘, 檜木達也, 余浩, 笠田竜太

    日本金属学会講演概要(CD-ROM) 163rd 2018

    ISSN: 2433-3093

  57. 爆発圧接による低放射化バナジウム合金異材接合材の試作

    長坂琢也, 長坂琢也, SHEN Jingjie, 室賀健夫, 室賀健夫, 外本和幸, 田中茂, 稲尾大介, 森園靖浩, 笠田竜太

    核融合エネルギー連合講演会(CD-ROM) 12th 2018

  58. 高エネルギー水冷ボールミルを用いたODS-Cuの開発

    八尾栄彰, 笠田竜太, 小西哲之, 大野直子, 鵜飼重治, 能登裕之, 菱沼良光, 室賀健夫

    日本原子力学会秋の大会予稿集(CD-ROM) 2017 2017

  59. Mechanical Properties of Electrodeposited Al-W Alloy Films and the Effects of Subsequent Heat Treatment

    Shota Higashino, Ayumu Takahashi, Ryuta Kasada, Masao Miyake, Tetsuji Hirato

    PRiME 2016, Honolulu, Hawaii, USA, 2016/10

  60. Nano-indentation study of electrodeposied Al-W alloy films

    Shota Higashino, Ayumu Takahashi, Masao Miyake, Ryuta Kasada, Tetsuji Hirato

    The 7th International Symposium of Advanced Energy Science 2016/09

  61. Electrodeposition of Al-W Alloy Films from Ionic Liquid and Evaluation of Their Corrosion Resistance and Mechanical Properties

    Shota Higashino, Ayumu Takahashi, Masao Miyake, Ryuta Kasada, Tetsuji Hirato

    229th ECS Meeting San Diego, CA, USA, May 31, 2016 (Poster) 2016/05

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    229th ECS Meeting San Diego, CA, USA, May 31, 2016 (Poster).

  62. 核融合原型炉への適用を目指した銅合金の中性子照射影響評価

    笠田竜太, 能登裕之, 大野直子, 室賀健夫, 鵜飼重治

    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) 33 2016

  63. Chemical State Mapping Analysis of Boron in Model B4C Control Rod under BWR Severe Accidential Condition by EPMA-SXES

    Kasada Ryuta, Ha Yoosung, Sakamoto Kan, Higuchi Toru

    Materia Japan 55 (12) 576-576 2016

    Publisher: The Japan Institute of Metals and Materials

    DOI: 10.2320/materia.55.576  

  64. Evaluation of mechanical properties of electrodeposited Al-W films

    Ayumu Takahashi, Shota Higashino, Masao Miyake, Ryuta Kasada, Tetsuji Hirato

    The 6th International Symposium of Advanced Energy Science, Uji Campus, Kyoto University, September 1-3. 2015, (Poster) 2015/09

  65. 革新的電力貯蔵装置による将来電力市場への原子力導入に関する考察(1)海洋を用いた革新的電力貯蔵装置と原子力による電力系統への影響

    武田秀太郎, 小西哲之, 櫻井繁樹, 笠田竜太

    日本原子力学会春の年会予稿集(CD-ROM) 2015 2015

  66. 高エネルギー水冷型ボールミルを用いた銅基ODS合金の開発

    笠田竜太, 井平椋太, 小西哲之, 大野直子, 能登裕之, 室賀健夫, 鵜飼重治

    日本金属学会講演概要(CD-ROM) 157th 2015

    ISSN: 2433-3093

  67. A View of Technology Maturity Assessment to Realize Fusion Reactor by Japanese Young Researchers

    KASADA Kyuta, GOTO Takuya, FUJIOKA Shinsuke, HIWATARI Ryoji, OYAMA Naoyuki, TANIGAWA Hiroyasu, MIYAZAWA Junichi, Young Scientists Special Interest Group on, Fusion Reactor Realization

    プラズマ・核融合学会誌 = Journal of plasma and fusion research 89 (4) 193-198 2013/04/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

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    技術成熟度(TRL;Technology Readiness Levels)評価法は,多様なプロジェクトにおける個々の技術の成熟度評価や異なる技術の成熟度の比較をサポートするための系統的な評価法として,様々な分野で活用が進められている,NASAが開発したプロジェクト・マネジメントツールである.これは,新技術開発プロセスを補助し,技術者と管理者を繋げるため,あるいは,科学・技術の進展度の共通理解のためのツールとして用いられている.核融合炉開発のTRL評価については,米国原型炉設計チーム(ARIESチーム)によって実施された例があるものの,多種多様な技術を含めたTRLに基づく系統的な評価はわが国では行われていない.これまでに,核融合炉若手実用化検討会等における若手有志により,多岐にわたる核融合炉工学技術開発のTRLの評価・分析を実施し議論することを通して,クリティカルな共通課題を異なる分野に跨る研究者間の共有知とするためにも,TRL評価法が有効であることが確認されている.本報では,TRL評価法の概要を説明し,本活動によって行われたわが国の核融合炉開発に対するTRL評価結果を示す.

  68. 核融合エネルギー変換を目的としたプラズマ対向機器の開発アプローチ;(3)レーザーフラッシュによる一方向性Cf /SiC 複合材料の熱伝導率評価 Peer-reviewed

    金成勲, 李泳柱, 檜木達也, 笠田竜太, 小西哲之, 尹漢基

    日本原子力学会 2013年春の年会 2013/03/26

  69. The Cycle and Span of Energy Generator in Sustainability Science

    (5) 9-12 2013

    Publisher: 京都大学生存基盤科学研究ユニット

    ISSN: 1883-0293

  70. Phase and Metal/Oxide Interface Structure of Nanoparticles in High-Cr Oxide Dispersion Strengthened Ferritic Steels with/without Al Alloying

    Peng Dou, Akihiko Kimura, Ryuta Kasada, Takanari Okuda, Masaki Inoue, Shigeharu Ukai, Somei Ohnuki, Toshiharu Fujisawa, Fujio Abe

    The 3rd Workshop On TEM With In Situ Irradiation, Hokkaido Univ., 2013.07.11-12. 2013

  71. 構造的に正しいLEGO版ITERをめざして(会員の声)

    笠田 竜太, 小西 哲之

    プラズマ・核融合学会誌 89 (11) 826-826 2013

    Publisher: プラズマ・核融合学会

  72. The evaluation of thermal conductivity of the unidirectional Cf/SiC composite for making low temperature gradient as divertor component Peer-reviewed

    S.H. Kim, Y.J. Lee, T. Hinoki, H.K. Yoon, R. Kasada, S. Konishi

    NuMat 2012: The Nuclear Materials Conference 2012/10/22

  73. ダイバ-タ用方向性Cf/SiC 複合材料の熱伝導率評価 Peer-reviewed

    金成勲, 李泳柱, 檜木達也, 笠田竜太, 小西哲之, 尹漢基

    日本原子力学会 2012年秋の年会 2012/09/19

  74. IFMIF/EVEDA事業のリチウムターゲット施設と試験施設の開発状況

    若井栄一, 杉本昌義, 木村晴行, 西谷健夫, 井田瑞穂, 金秉俊, GROESCHEL F., 山本道好, 横峰健彦, 吉田崇英, 木村晃彦, 笠田竜太, 野上修平, 西村新, 栗下裕明, 深田智, 辻義之, 帆足英二, 鈴木幸子, 堀池寛, 芹澤久, 川人洋介, 水谷正海, 鈴木晶大, 八木重郎, 寺井隆幸, 近藤浩夫, 金村卓治, 渡辺一慶, 新妻重人, 藤城興司, 古川智弘, 平川康, 平野美智子, 菊地孝行, 中村和幸

    核融合エネルギー連合講演会(CD-ROM) 9th 2012

  75. 低放射化フェライト鋼の二重イオン照射影響評価

    高山嘉幸, 久保博史, 安堂正巳, 濱口大, 谷川博康, 近藤創介, 笠田竜太, 木村晃彦

    核融合エネルギー連合講演会(CD-ROM) 9th 2012

  76. 低放射化フェライト鋼上に作製したタングステン皮膜の接合強度評価 Peer-reviewed

    佐藤学, 鬼柳任, 長坂琢也, 笠田竜太, 木村晃彦

    日本原子力学会2012 年春の年会,福井大学文京キャンパス,2012.3.19-21 2012

  77. High-Cr ODS Steels R&D for Advanced Nuclear Systems Peer-reviewed

    A. Kimura, H.I. Je, Y.S Ha, H. Noto, D. Chen, N. Iwata, R. Kasada, K. Morishita, T. Okuda, S. Ohnuki, S. Ukai, M. Inoue, P. Dou, S.H. Noh, A. Hasegawa

    The 2nd Japanese-German Workshop on Energy Materials Science,Karlsruhe Institute of Technology, Germany,2012.12.11-14 2012

  78. Structural Materials Innovation - Radiation Tolerance - Peer-reviewed

    A. Kimura, H.I. Je, Y.S. Ha, H. Noto, D. Chen, N. Iwata, R. Kasada, T. Okuda, S. Ohnuki, S. Ukai, M. Inoue, P. Dou, A. Hasegawa

    27th Symposium on Fusion Technology (SOFT2012)The Palais des Congrès of Liège, Liège, Belgium,2012.9.24-26 2012

  79. High-Cr ODS Steels R&D for Advanced Nuclear Systems -Keys of high performance –, Peer-reviewed

    A. Kimura, H.I. Je, Y.S Ha, H. Noto, D. Chen, N. Iwata, R. Kasada, K. Morishita, T. Okuda, S. Ohnuki, S. Ukai, M. Inoue, P. Dou, S.H. Noh, A. Hasegawa

    ODS Alloys for Nuclear Applications Workshop,University of Oxford,2012.9.24-26 2012

  80. The Mechanism of Dispersion Strengthening in Super ODS Steel Peer-reviewed

    A. Kimura, R. Kasada, N. Iwata, J. Isselin, P. Dou, J.H. Lee, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

    6th International Conference on Creep, Fatigue and Creep-Fatigue Interaction (CF-6),Radisson Blu Resort Temple Bay, Mamallapuram, Tamil Nadu, India,2012.11.22-25 2012

  81. ブランケットの高性能化に向けた先進鉄鋼材料の開発 Peer-reviewed

    木村晃彦, 笠田竜太, 長谷川晃, 野上修平

    プラズマ・核融合学会第29回年会,クローバープラザ、春日市、福岡,2012.11.27-30 2012

  82. 原型炉実現に向けた低放射化フェライト鋼研究開発の進展

    芝清之, 笠田竜太, 野上修平, 中田隼矢, 大久保成彰

    プラズマ・核融合学会誌 87 (3) 187-194 2011/03

  83. IFMIF/EVEDA事業のテストセル系テーマにおける日本チームの活動状況

    若井栄一, 小河原貴史, 菊地孝行, 山本道明, MOLLA Joaquin, 木村晃彦, 笠田竜太, KIM Byungjun, 野上修平, 長谷川晃, 栗下裕明, 江原真司, 伊藤譲, 斎藤正博, 阿部勝憲, 西村新, 横峯健彦

    日本原子力学会春の年会予稿集(CD-ROM) 2011 2011

  84. 二重イオンビーム照射施設(DuET)を用いた核融合炉材料の照射影響評価

    橋冨興宜, 近藤創介, 岩田憲幸, 笠田竜太, 檜木達也, 木村晃彦

    日本金属学会講演概要(CD-ROM) 149th 2011

    ISSN: 2433-3093

  85. Zr水素化物のイオン照射硬化

    大野直子, 長谷川晃子, 笠田竜太, 近藤創介, 橋冨興宣, 松井秀樹, 木村晃彦, 樋口徹, 坂本寛, 中司雅文

    日本金属学会講演概要(CD-ROM) 149th 2011

    ISSN: 2433-3093

  86. マルチスケール材料評価基盤施設(MUSTER)を用いたエネルギー材料研究

    大村高正, 岩田憲幸, 近藤創介, 笠田竜太, 檜木達也, 木村晃彦

    日本金属学会講演概要(CD-ROM) 149th 2011

    ISSN: 2433-3093

  87. 陽電子消滅分光法を用いたFe-Cr二元系合金の相分離現象の検出

    佐藤紘一, 笠田竜太

    日本金属学会 2011年秋期大会 2011

  88. Effects of Ion-irradiation on hardness of Zr-hydrides (delta-hydride)

    Higuchi Toru, Sakamoto Kan, Nakatsuka Masafumi, Oono Naoko, Hasegawa Akiko, Kondo Sosuke, Hashitomi Okinobu, Kasada Ryuta, Matsui Hideki, Kimura Akihiko, Muta Hiroaki, Kimura Hiroaki

    Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan 2011 (0) 492-492 2011

    Publisher: 一般社団法人 日本原子力学会

    DOI: 10.11561/aesj.2011s.0.492.0  

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    照射環境下におけるジルコニウム水素化物の機械特性を把握することを目的としてバルク状の&amp;delta;相水素化物に加速器照射を実施し、非照射領域および照射領域における超微小硬さ測定を行った。約5 dpaのFeイオン照射によって、硬さが1.2倍程度まで増大することが確認された。

  89. Hardness Distribution of Friction Stir Processed ODS Ferritic Steel after Neutron Irradiation Peer-reviewed

    S.H. Noh, R. Kasada, A. Kimura, M.A. Sokolov

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

  90. System Integration Study of W-Armored Structure Components Peer-reviewed

    A. Kimura, S. Noh, Y. Himei, R. Kasada, K. Tokunaga, T. Tokunaga, H. Watanabe, N. Yoshida, T. Nagasaka, M. Tokitani, T. Muroga, S. Nogami, Y. Ueda, M. Sato, Y. Hatano, Y. Oya

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

  91. 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

  92. The Effect of Strain Rate on the High Temperature Tensile Properties of ODS Ferritic Steels Peer-reviewed

    H.I. Je, R. Kasada, A. Kimura

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

  93. 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

  94. Phase and Metal/Oxide Interface Structure of Nanoparticles in High-Cr Oxide Dispersion Strengthened Ferritic Steels with Different Titanium Contents Peer-reviewed

    P. Dou, A. Kimura, R. Kasada, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

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

  95. 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

  96. Positron annihilation studies on ODS ferritic alloys, Asian-Core University Program on Advanced Energy Science, Peer-reviewed

    R. Kasada, K. Sato, Q. Xu, S.H. Noh, T. Yoshiie, A. Kimura

    International Symposium on Advanced Energy Systems and Materials, Pukyon National University, Busan, Korea, 2011.3.4-5 2011

  97. 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

  98. Strain Rate Effects on High-Temperature Tensile Properties of Several Types of Steels, Peer-reviewed

    H.I Je, R. Kasada, A. Kimura

    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

  99. 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

  100. Measurement of Bonding Strength between Tungsten Coating and Reduced Activation Ferritic Steel Peer-reviewed

    M. Satou, T. Oniyanagi, K. Abe, T. Nagasaka, R. Kasada, A. Kimura

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

  101. 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

  102. 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

  103. ODSインサート材を用いたTLP接合部微細化技術開発 Peer-reviewed

    H. Noto, R. Kasada, A. Kimura, S. Ukai

    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

  104. Development of a tensile testing device under ion irradiation and study on effect of stress on radiation embrittlement

    藤井 克彦, 福谷 耕司, 笠田 竜太

    INSS journal 18 198-210 2011

    Publisher: 原子力安全システム研究所

    ISSN: 1340-4482

  105. 高速炉燃料被覆管材料「スーパーODS鋼」--高Crフェライト系酸化物分散鋼の開発研究

    木村 晃彦, 笠田 竜太, 奥田 隆成

    配管技術 52 (13) 5-9 2010/11

    Publisher: 日本工業出版

    ISSN: 0385-9894

  106. Simulation of Leak Limit Strain for Internally Pressurized Pipe with Circumferential Surface Flaw

    OHATA Mitsuru, KASADA, KIMURA Akihiko, SHIBA Kiyoyuki, TANIGAWA Hiroyasu

    87 210-211 2010/08/18

  107. Compatibility of SiC in Liquid Blanket

    KONISHI Satoshi, PARK Changho, KASADA Ryuta, NOBORIO Kazuyuki

    Journal of plasma and fusion research 86 (7) 417-419 2010/07/25

    Publisher: プラズマ・核融合学会

    ISSN: 0918-7928

  108. 低放射化フェライト・マルテンサイト鋼接合部の損傷組織に及 ぼすガス原子の効果 Peer-reviewed

    橋本直幸, 長坂琢也, 笠田竜太, 檜木達也, 木村晃彦, 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

  109. VPS‐タングステン被覆低放射化フェライト・マルテンサイト 鋼の耐熱疲労特性向上に関する研究 Peer-reviewed

    徳永知倫, 渡邉英雄, 長坂琢也, 笠田竜太, 時谷政行, 吉田直亮, 木村晃彦, 檜木達也, 室賀健夫, 光原昌寿, 中島英治, 増崎貴, 江里幸一郎, 鈴木哲, 秋場真人, 橋本直幸, 大貫惣明, 鵜飼重治, M. Sokolov, T. Amamoto

    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

  110. 低合金鋼の照射硬化とミクロ組織変化に対する応力下照射の影響 Peer-reviewed

    藤井克彦, 福谷耕司, 笠田竜太, 木村晃彦, 大久保忠勝

    日本原子力学会2010年春の年会,茨城大学水戸キャンパス,2010.3.26-28 2010

    DOI: 10.11561/aesj.2010s.0.406.0  

  111. 曲げ応力下で照射した低合金鋼の照射硬化とミクロ組織変化 Peer-reviewed

    藤井克彦, 福谷耕司, 大久保忠勝, 笠田竜太, 木村晃彦

    日本金属学会2010年春期(第146回)大会,筑波大学,2010.3.28-30 2010

  112. オーステナイトステンレス鋼のSCC発生時における不動態被膜厚さの影響 Peer-reviewed

    中川雄仁, 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

  113. SUS316L鋼のSCC感受性に及ぼす溶存水素の影響 Peer-reviewed

    中川雄仁, 濃野真広, 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

  114. Mechanical Properties of ODS Steel and Tungsten Joints with Different Insert layers for Fusion Applications Peer-reviewed

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

    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

  115. Effect of Hydrogen on oxidation behavior in SUS316L under high temperature water Peer-reviewed

    K. Nakagawa, R. Kasada, A. Kimura

    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

  116. Development of Small Specimen Testing Technologies on Fracture Toughness of Phosphorus added F82HSteel Peer-reviewed

    B.J. Kim, R. Kasada, A. Kimura, 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

  117. Microstructures and Radiation Damage in Al-added High-Cr ODS Ferritic Steels Peer-reviewed

    C.H. Zhang, J.S. Jang, A. Kimura, R. Kasada, Y.T. Yang, H.D. Cho

    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

  118. 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

  119. Oxide particles Characterization in Al-alloyed ODS Steels Peer-reviewed

    P. Dou, A. Kimura, R. Kasada, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

    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

  120. Fracturetoughness and Charpy impact properties of P-added F82H steels Peer-reviewed

    B.J. Kim, R. Kasada, A. Kimura, H. Tanigawa

    OECD Nuclear Energy Agency International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS), International Nuclear Training and Education Center, KAERI, Daejeon, Korea, 2010.8.31-9.3 2010

  121. Super ODS steels R&D for fuel cladding of advanced nuclear systems Peer-reviewed

    A. Kimura, R. Kasada, N. Iwata, J. Isselin, P. Dou, J.H. Lee, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe

    OECD Nuclear Energy Agency International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS), International Nuclear Training and Education Center, KAERI, Daejeon, Korea, 2010.8.31-9.3 2010

  122. ヘリウムイオン照射されたFeの低速陽電子ビームを用いた陽電子寿命測定

    佐藤紘一, 木野村淳, 大村高正, 徐?, 義家敏正, 笠田竜太, 木村晃彦, 森下和功

    日本金属学会 2010年秋期大会 2010

  123. イオン照射したフェライト系鉄鋼材料における超微小硬さ Peer-reviewed

    高山嘉幸, 笠田竜太, 薮内清皓, 木村晃彦, 谷川博康

    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

  124. ネオジム磁石のCu粒界拡散処理(Cu-GBD)による保磁力低下 Peer-reviewed

    大野直子, 笠田竜太, 松井秀樹, 木村晃彦, 佐川眞人

    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

  125. 微小試験片による低放射化フェライト鋼の破壊靭性評価法に関する研究 Peer-reviewed

    金秉俊, 笠田竜太, 木村晃彦, 若井栄一, 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

  126. 低合金鋼の照射硬化に対する応力下照射の影響 Peer-reviewed

    藤井克彦, 福谷耕司, 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

  127. Corrosion behavior of ODS ferritic steels made from elemental and pre-alloyed powders Peer-reviewed

    J H Lee, R Kasada, A Kimura, T Okuda, M Inoue, S Ukai, S Ohnuki, T Fujisawa, F Abe

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

  128. Evaluation14th International Conference on Fusion Reactor Materials (ICFRM-14 Peer-reviewed

    J Isselin, R Kasada, A Kimura, T Okuda, M Inoue, S Ukai, S Ohnuki, T Fujiwara, T F Abe

    14th International Conference on Fusion Reactor Materials (ICFRM-14), Sapporo Convention Center, 2009.9.6-11 2009

  129. Effects of Zirconium on the Microstructure and Mechanical Properties of High Cr ODS Ferritic Steels Peer-reviewed

    P Dou, R Kasada, A Kimura, T Okuda, M Inoue, S Ukai, S Ohnuki, T Fujisawa, F Abe

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

  130. Liquid phase diffusion bonding between ODS steel and W Peer-reviewed

    N Oono, R Kasada, N Y Iwata, A Kimura

    14th International Conference on Fusion Reactor Materials (ICFRM-14), Sapporo Convention Center, 2009.9.6-11 2009

  131. Effects of specimen size on the impact properties of welded A533B steels Peer-reviewed

    B J Kim, R Kasada, A Kimura

    2009年度 軽水炉燃料・材料・水化学 夏期セミナー,ホテル玉泉,2009.7.2-4 2009

  132. Evaluation of mechanical properties in weld-joint of F82H by using small specimens Peer-reviewed

    R Kasada, B J Kim, A Kimura, M Ando, H Tanigawa

    9th International Symposium on Fusion Nuclear Technology (ISFNT-9), Dalian, China, 2009.10.12 2009

  133. Facture Toughness and Ductile-Brittle Transition Behavior of ODS Ferritic Steels Peer-reviewed

    R Kasada, S G Lee, T Omura, A Kimura

    14th International Conference on Fusion Reactor Materials (ICFRM-14), Sapporo Convention Center, 2009.9.6-11 2009

  134. Influene of Temperature and Compositions on Corrosion Resistance of ODS Ferritic Steels Peer-reviewed

    李載勲, 笠田竜太, 木村晃彦

    日本金属学会2009年春期大会,東京工業大学,2009.3.23-25 2009

  135. 高耐食性ODS鋼のクリープ変形挙動 Peer-reviewed

    戸田佳明, 原徹, 阿部冨士雄, 木村晃彦, 笠田竜太, 井上賢紀, 奥田隆成, 大貫惣明, 鵜飼重治, 藤澤敏治

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

  136. 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

  137. 液相拡散接合した ODS 鋼の微細組織および強度特性, Peer-reviewed

    盧相熏, 笠田竜太, 大野直子, 岩田憲幸, 木村晃彦

    日本金属学会2009年秋期(第145回),京都大学吉田キャンパス,2009.9.15-17 2009

  138. Dy改質処理を施したネオジム磁石の微細構造の研究 Peer-reviewed

    大野直子, 笠田竜太, 松井秀樹, 木村晃彦, 今成文郎, 佐川眞人

    日本金属学会2009年秋期(第145回),京都大学吉田キャンパス,2009.9.15-17 2009

  139. タングステン被覆バナジウム合金の熱物性および機械的特性 Peer-reviewed

    長坂琢也, 室賀健夫, 笠田竜太, 岩田憲幸, 木村晃彦

    日本金属学会2008年秋期(143回)大会,熊本大学,2008.9.23-25 2008

  140. 圧力容器溶接部の脆化評価のための微小試験片技術の開発 Peer-reviewed

    三井秀晃, 笠田竜太, 木村晃彦

    日本金属学会2008年秋期(143回)大会,熊本大学,2008.9.23-25 2008

  141. フェライト鋼の衝撃特性に及ぼす試験片サイズ効果 Peer-reviewed

    三井秀晃, 笠田竜太, 木村晃彦

    第7回核融合エネルギー連合講演会,青森市民ホール,2008.6.19-21 2008

  142. 酸化物分散強化合金の硬度に及ぼす結晶粒度の影響 Peer-reviewed

    李載勲, 笠田竜太, 木村晃彦

    第7回核融合エネルギー連合講演会,青森市民ホール,2008.6.19-21 2008

  143. 先進原子力システム用酸化物分散強化鋼の創製(1)粉体特性に及ぼすMA条件の影響 Peer-reviewed

    岩田憲幸, 笠田竜太, 木村晃彦

    粉体粉末冶金協会平成20年度春季大会(第101回講演大会),早稲田大学国際会議場,2008.5.27-29 2008

  144. Effect of Aluminum on Corrosion Resistance of ODS Ferritic steels in Supercritical Water Peer-reviewed

    李載勲, 笠田竜太, 木村晃彦

    日本金属学会2008年秋期(143回)大会,熊本大学,2008.9.23-25 2008

  145. The Mechanism of Irradiation Hardening Accompanied by No-Loss-of-Elongation in ODS steels Peer-reviewed

    A Kimura, R Kasada, H Kishimoto, H S Cho, J H Lee, N Toda, T Shinohara

    Materials Science &Technology 2008 conference and Exhibition (Ms&T'08), David Lawrence Convention Center, 2008.10.5-9 2008

  146. R&D on Materials Engineering for DEMO Blanket: Objective Peer-reviewed

    H Tanigawa, E Wakai, S Jitsukawa, Komazaki, Y Kohno, R Kasada, K Morishita, A Kimura, Hashimoto, S Ohnuki, H Abe Nogami

    implementation in 2007 and 2008, progress, schedule (whole period and breakdown for 2007 and 2008), 2nd Workshop on DEMO in the Broader Approach Activities, Japan Atomic Energy Agency, Tokyo, Japan, 2008.1.28-30 2008

  147. 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

  148. The Mechanism of Irradiation Hardening of Iron Model Alloys Peer-reviewed

    A Kimura, T Kudo, R Kasada, M Saitoh, H Yano

    第16回環太平洋原子力会議, 青森市文化会館, 2008.10.13-18 2008

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

    大野直子, 笠田竜太, 岩田憲幸, 岸本弘立, 木村晃彦

    日本金属学会2008年秋期(143回)大会,熊本大学,2008.9.23-25 2008

  150. 先進ブランケット用ODS鋼の微細組織観察 Peer-reviewed

    盧相熏, 岩田憲幸, C.H. Zhang, 笠田竜太, 木村晃彦

    第7回核融合エネルギー連合講演会,青森市民ホール,2008.6.19-21 2008

  151. Grain Boundary Phosphorus Segregation under Thermal Aging in Low Alloy Steels

    43 13-24 2007/03/01

    Publisher: 近畿大学原子力研究所

    ISSN: 0374-8715

  152. Development of an Extensive Database of Mechanical Properties for Reduced Activation Ferritic/Martensitic Steels Peer-reviewed

    H Tanigawa, K Shiba, M Ando, T Hirose, R Kasada, E Wakai, S Jitsukawa, A Kimura, Y Kohno, A Kohyama, R L Klueh, M Sokolov, T Yamamoto, R Stoller, G Odette, R J Kurtz, S Zinkle

    Thirteenth International Conference on Fusion Reactor Materials (ICFRM-13), Nice Acropolis, Nice, France, 2007.12.9-14 2007

  153. Resolution/precipitation behavior of Y2O3 in mechanically alloyed iron alloy powders Peer-reviewed

    李載勲, Q Xu, 義家敏正, 笠田竜太, 木村晃彦

    日本金属学会2007年秋期大会,岐阜大学,2007.9.19-21 2007

  154. Roles of Grain Size on the Performance of Ferritic Alloys Peer-reviewed

    J.H. Lee, R. Kasada, A. Kimura

    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

  155. Cross-cutting Materials Issues for Super ODS Steels Peer-reviewed

    A Kimura, H S Cho, R Kasada, H Kishimoto, N Iwata, S Ukai, S Ohnuki, T Fujisawa

    Thirteenth International Conference on Fusion Reactor Materials (ICFRM-13), Nice Acropolis, Nice, France, 2007.12.9-14 2007

  156. Super ODS Steels R&D for Cladding of Next Generation Nuclear Systems Peer-reviewed

    A Kimura, H S Cho, N Toda, R Kasada, H Kishimoto, N Iwata, S Ukai, S Ohnuki, T Fujisawa

    The Sixth Pacific Rim International Conference on Advanced Materials and Processing (PRICM-6), ICC Jeju, Jeju Island, Korea, 2007.11.5-9 2007

  157. Recent Progress on Super ODS Steels R&D for Cladding of Highly Efficient Nuclear Plant Peer-reviewed

    A Kimura, H S Cho, N Toda, R Kasada, H Kishimoto, N Iwata, S Ukai, S Ohnuki, T Fujisawa

    9th China-Japan Symposium on Fission/Fusion Technology, Quirin, China, 2007.10.22-26 2007

  158. Studies on Irradiation Effects of ODS Steels by Using DuET Facility Peer-reviewed

    R Kasada, H Takahashi, K Yutani, H Kishimoto, O Hashitomi, A Kimura

    9th China-Japan Symposium on Fission/Fusion Technology, Quirin, China, 2007.10.22-26 2007

  159. Effects of High Dose Ion-Irradiation on Super-ODS Ferritic Steels Peer-reviewed

    H Kishimoto, R Kasada, A Kimura, O Hashitomi

    Thirteenth International Conference on Fusion Reactor Materials,(ICFRM-13), Nice, France, 2007.12.10-14 2007

  160. Technical Issues of RafmS for the Fabrication of ITER Test Blanket Module Peer-reviewed

    H Tanigawa, T Hirose, K Shiba, R Kasada, E Wakai, H Serizawa, K Yousuke, S Jitsukawa, A Kimura, Y Kohno, A Kohyama, S Katayama, R L Klueh, M A Sokolov, R E Stoller

    8th International Symposium on Fusion Nuclear Technology (ISFNT-8), Hidelberg, Germany, 2007.9.30-10.5 2007

  161. ,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

  162. Effect of Helium on Mechanical Properties of High Chromium ODS Ferritic/Martensitic Steels for Fusion Applications

    HASEGAWA A, KAKINUMA N, NOGAMI S, SATOU M, ABE K, KASADA R, KIMURA A, JITSUKAWA S

    CYRIC Annu Rep (Cyclot Radioisot Cent Tohoku Univ) 2007 21-24 2007

    Publisher: Cyclotron and Radioisotope Center, Tohoku University

  163. Development of Test-cell for IFMIF

    A. Shimizu, A. Kimura, R. Kasada, H. Kurishita, M. Baba

    J. Plasma and Fusion Res. 82 3-12 2006

  164. 高クロム酸化物分散強化フェライト鋼の時効脆化評価 Peer-reviewed

    奥田直之, 笠田竜太, 木村晃彦

    日本原子力学会2006年秋の大会,北海道大学,2006.9.27-29 2006

    DOI: 10.11561/aesj.2006f.0.500.0  

  165. 高クロム酸化物分散強化鋼における時効脆化の微細組織学的要因に関する研究 Peer-reviewed

    奥田直之, 笠田竜太, 木村晃彦

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

  166. Characterization of Mechanical Alloyed Fe-Ti-Y2O3 Powders with Heat Treatment Peer-reviewed

    J.H. Lee, R. Kasada, A. Kimura

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

  167. Deformation Microstructures of Thermal-Aged and Neutron-Irradiated Peer-reviewed

    R. Kasada, N. Toda, H.S. Cho, N. Okuda, A. Kimura

    23rd Symposium on Effects of Radiation on Materials, Dolce Hayes Mansion,San Jose, USA,2006.6.13-15 2006

  168. Mechanism of Irradiation Hardening with No-loss-of-elongation in ODS Steels Peer-reviewed

    A. Kimura, N. Toda, R. Kasada

    23rd Symposium on Effects of Radiation on Materials, Dolce Hayes Mansion,San Jose, USA,2006.6.13-15 2006

  169. 酸化物分散強化(ODS)鋼のスウェリングに及ぼすCr量の影響 Peer-reviewed

    高橋宏昌, 湯谷健太郎, 岸本弘立, 笠田竜太, 木村晃彦

    日本原子力学会2006年秋の大会,北海道大学,2006.9.27-29 2006

    DOI: 10.11561/aesj.2006f.0.795.0  

  170. 9Cr系ODS鋼における高濃度ヘリウム照射効果 Peer-reviewed

    高橋宏昌, 岸本弘立, 笠田竜太, 木村晃彦

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

  171. 酸化物分散強化フェライトステンレス鋼の時効脆化 Peer-reviewed

    笠田竜太, 奥田直之, Cho Hang-Sik, 木村晃彦

    日本金属学会2005年秋期(第137回)大会,広島大学,2005.9.28-30 2005

  172. Effects of Neutron Irradiation on the Mechanical Properties of High-Cr ODS Steels Peer-reviewed

    H.S. Cho, R. Kasada, A. Kimura, S. Ukai, M. Fujiwara

    日本金属学会2005年秋期(第137回)大会,広島大学,2005.9.28-30 2005

  173. Master Curve Evaluation of Transition Fracture Toughness of a JLF-1 Reduced-Activation Ferritic Steel Peer-reviewed

    R. Kasada, A. Kimura

    The 12th International Conference on Fusion Reactor Material (ICFRM-12),Santa Barbara, USA,2005.12.4-9 2005

  174. Ferritic Steel-Blanket Systems Integration R&D Peer-reviewed

    A. Kimura, R. Kasada, A. Kohyama, M. Enoeda, M. Akiba, S. Jitsukawa

    The Seventh International Symposium on Fusion Nuclear Technology (ISFNT-7),Tokyo,2005.5.22-27 2005

  175. 重イオン照射を用いた高温重照射環境におけるODS鋼の酸化物分散粒子安定性評価 Peer-reviewed

    岸本弘立, 湯谷健太郎, 笠田竜太, 木村晃彦

    日本金属学会2005年秋期(第137回)大会,広島大学,2005.9.28-30 2005

  176. Effects of Alloying Elements on Mechanical Properties of Reduced Activation Ferritic Steels Peer-reviewed

    N. Toda, H. Ono, R. Kasada, H. Sakasegawa, T. Hirose, A. Kimura, A. Kohyama

    The 2nd International Symposium on Sustainable Energy System,Kyoto,2004.12.17-18 2004/12/17

  177. Irradiation Hardening and Microstructure Changes in ODS Steels Peer-reviewed

    N. Toda, R. Kasada, A. Kimura, S. Ukai

    The 2nd International Symposium on Sustainable Energy System,Kyoto,2004.12.17-18 2004/12/17

  178. 低放射化フェライト鋼の照射硬化挙動に及ぼす微量添加元素の影響 Peer-reviewed

    笠田竜太, 木村晃彦, 戸田直樹, 小野広展

    日本金属学会2004年秋期(第135回)大会,秋田市,秋田大学手形キャンパス,2004.9.28-30 2004

  179. 鉄二元系モデル合金の照射硬化におよぼす添加元素の影響 Peer-reviewed

    齋藤匡史, 笠田竜太, 工藤健, 戸田直樹, 木村晃彦

    日本金属学会2004年春期(第134回)大会,東京都,2004.3.30-4.1 2004

  180. Irradiation Hardening and Post-Irradiation Annealing Recovery Behavior in Iron-Based Binary Alloys Peer-reviewed

    R. Kasada, T. Kudo, M. Saito, A. Kimura

    The 22nd Symposium on Effects of Radiation on Materials,Boston, USA,2004.6.8-10 2004

  181. Investigation of Neutron Dose and Dose Rate Effects on the Radiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel Peer-reviewed

    R. Kasada, T. Kudo, A. Kimura, H. Matsui, M. Narui

    The 22nd Symposium on Effects of Radiation on Materials,Boston, USA,2004.6.8-10 2004

  182. Effects of Neutron Irradiation on the grain Boundary Segregation of P in A533B Steel Peer-reviewed

    A. Kimura, M. Shibata, R. Kasada, M. Fujii, K. Fukuya

    The 22nd Symposium on Effects of Radiation on Materials,Boston, USA,2004.6.8-10 2004

  183. 酸化物分散強化(ODS)鋼の変形挙動 Peer-reviewed

    戸田直樹, 笠田竜太, 木村晃彦, 鵜飼重治

    日本金属学会2004年秋期(第135回)大会,秋田市,秋田大学手形キャンパス,2004.9.28-30 2004

  184. ODS鋼の耐照射脆化特性 Peer-reviewed

    戸田直樹, 笠田竜太, 木村晃彦, 鵜飼重治

    第5回核融合エネルギー連合講演会,仙台市,仙台市民会館,2004.6.17-18 2004

  185. ODS鋼における伸びの低下を伴わない照射硬化挙動 Peer-reviewed

    戸田直樹, 笠田竜太, 木村晃彦, 鵜飼重治, 藤原優行

    日本金属学会2004年春期(第134回)大会,東京都,2004.3.30-4.1 2004

  186. Small Specimen Test Technology -Development of Fracture Toughness Testing with Miniaturized Specimen

    H.Kurishita, T.Yamamoto, T.Nagasaka, A.Nishimura, T.Muroga, S.Jitsukawa, A.Kimura, Y.Kato, K.Morishita, R.Kasada, H.Kubo, M.Narui, Y.Kohno, H.Serizawa

    JAERI-Tech, 2003-005, IFMIF, KEP Report 433-442 2003

  187. Factors Controlling Irradiation Hardening of Fe Model Alloys Peer-reviewed

    T. Kudo, R. Kasada, A. Kimura, H. Nakata, K. Fukuya, H. Matsui, M. Narui

    11th International Conference on Fusion Reactor Materials (ICFRM-11) 2003

  188. Microstructural Analysis of Reduced-Activation Ferritic Steel Irradiated with Nickel-Addition Techniques Peer-reviewed

    R. Kasada, A. Kimura, D.S. Gelles, R.J. Kurtz, M.B. Toloczko

    11th International Conference on Fusion Reactor Materials (ICFRM-11) 2003

  189. Materials R&D for Safe and Highly Efficient Operation of Advanced Nuclear Power Plant Peer-reviewed

    T. Kudo, M. Shibata, H. Ono, R. Kasada, A. Kimura, T. Fujii, K. Fukuya

    The 1st International Symposium on Sustainable Energy System,京都 2003

  190. Effect of Tantalum,Titanium,Nitrogen,and Boron on Mechanical Properties of Reduced-Activation Ferritic Steels Peer-reviewed

    N. Toda, H. Ono, H, Sakasegawa, R. Kasada, A. Kimura, Y. Kohno, A. Kohyama

    11th International Conference on Fusion Reactor Materials 2003

  191. 核融合炉用鉄鋼材料の破壊靭性値評価のための微小試験片技術開発 Peer-reviewed

    小野広展, 久保博嗣, 笠田竜太, 木村晃彦

    日本金属学会2003年秋期大会,2003 2003

  192. 低放射化フェライト鋼「JLF-1」の破壊靭性に及ぼす試験片サイズ効果 Peer-reviewed

    小野広展, 笠田竜太, 木村晃彦

    日本金属学会2003年春期大会,2003 2003

  193. 低放射化マルテンサイト鋼 「JLF-1-3rdHeat」の材料特性 Peer-reviewed

    笠田竜太, 松下悠哉, 酒瀬川英雄, 廣瀬貴規, 木村晃彦, 香山晃

    第4回核融合エネルギー連合講演会,2002 2002

  194. Grain Boundary Segregation of Phosphorus in Reactor Vessel Steels Peer-reviewed

    H. Nakata, K. Fukuya, K. Fujii, M. Shibata, R. Kasada, A. Kimura

    International Symposium on Mechanisms of Material Degradation and Non-Destructive Evaluation in Light Water Reactors,大阪, 2002

  195. Neutron Dose and Dose Rate Effects on the Irradiation Hardening of Reactor Pressure Vessel Steel Peer-reviewed

    R. Kasada, T. Kudo, A. Kimura, H. Matsui, M. Narui

    International Symposium on Mechanisms of Material Degradation and Non-Destructive Evaluation in Light Water Reactors,大阪 2002

  196. Helium Accumulation Behavior during Irradiation Damage in Iron Peer-reviewed

    R. Sugano, K. Morishita,H. Iwakiri, R. Kasada, A. Kimura, N. Yoshida

    CREST International Symposium on SiC/SiC Composite Materials R&D and Its Application to Advanced Energy Systems,京都 2002

  197. フェライト鋼の照射損傷におよぼすヘリウムの影響 (3)-Fe-Cr二元合金におけるヘリウム放出挙動- Peer-reviewed

    菅野隆一朗, 森下和功, 笠田竜太, 木村晃彦, 岩切宏友, 吉田直亮

    日本金属学会2002年秋期(第131回)大会,2002 2002

  198. 鉄-銅モデル合金における電子線照射効果と照射後焼鈍回復挙動 Peer-reviewed

    工藤健, 笠田竜太, 木村晃彦, 中田早人, 福谷耕司, 松井秀樹, 鳴井實

    日本金属学会2002年秋期(第131回)大会,2002 2002

  199. Fe-Cuモデル合金における照射硬化への損傷速度の影響 (「原子炉圧力容器材料の照射脆化機構」研究会報告)

    北尾 健, 笠田 竜太, 森下 和功

    KURRI-KR (62) 141-149 2001/03

    Publisher: 京都大学原子炉実験所

    ISSN: 1342-0852

  200. Review of helium effects on irradiation embrittlement in reduced activation ferritic steels Peer-reviewed

    A Kimura, R Kasada, K Morishita, R Sugano, A Kohyama, T Yamamoto, H Matsui, A Hasegawa, K Abe, N Yamamoto

    PRICM 4: FORTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, VOLS I AND II 1431-1434 2001

  201. 「低放射化マルテンサイト鋼の空孔集合体形成挙動に及ぼす照射温度履歴・ヘリウムの影響」 Peer-reviewed

    笠田竜太, 木村晃彦, 松井秀樹

    日本金属学会2001年春期(第128回)大会,2001年3月28-30日,千葉工業大学,千葉県習志野市 2001

  202. 「重イオン照射による鉄基合金の損傷組織とその評価方法の開発」 Peer-reviewed

    上坂 充, 岩井岳夫, 助川敏男, 宮 健三, 森下和功, 北尾健, 笠田竜太, 菅野隆一朗, 木村晃彦, 加藤雄大, 谷川博康, 安堂正巳, 香山 晃, 渡辺英雄, 浜口 大

    2001年1月11日HITシンポジウム,東京大学,東京都千代田区 2001

  203. Correlation between Neutron Irradiation-Induced Hardening and Microstructural Changes in Iron-Copper Model Alloys Irradiated at Different Neutron Dose Rates Peer-reviewed

    T. Kitao, R. Kasada, K. Morishita, H. Matsui, A. Kimura

    Proc. of PRICM4,1,1465-1468 2001

  204. 低放射化フェライト鋼の核融合模擬環境下における材料挙動評価 Peer-reviewed

    木村晃彦, 笠田竜太, 菅野隆一朗, 森下和功, 香山晃, 長谷川晃, 阿部勝憲, 山本琢也, 松井秀樹, 山本徳和, 吉田直亮

    プラズマ・核融合学会第18回年会,2001 2001

  205. 低放射化フェライト鋼の耐ヘリウム脆化特性 Peer-reviewed

    木村晃彦, 笠田竜太, 菅野隆一朗, 森下和功, 松井秀樹, 長谷川晃

    日本金属学会2001年秋期(第129回)大会,2001 2001

  206. High Performance of Reduced Activation Ferritic Steels Under Fusion Environment Peer-reviewed

    A. Kimura, R. Kasada, A. Kohyama, H. Matsui, A. Hasegawa, K. Abe

    Symposium on Advanced Research of Energy Technology 2000,札幌, 2000

  207. 「低放射化フェライト鋼の耐中性子照射性と開発の現状」 Peer-reviewed

    木村晃彦, 森下和功, 笠田竜太, 菅野隆一朗, 香山 晃, 広瀬貴則, 松井秀樹, 山本琢也, 阿部勝憲, 長谷川晃, 三沢俊平

    第3回核融合エネルギー連合講演会,2000年6月12日-13日,中部大学,愛知県春日井市 2000

  208. 「低温ヘリウム注入した低放射化マルテンサイト鋼の照射後焼鈍によるキャビティ形成過程」 Peer-reviewed

    菅野隆一朗, 笠田竜太, 木村晃彦

    日本金属学会1999年秋期大会,金沢,1999年9月28日~30日 1999

  209. ”Effects of Helium Implantation on Reduced Activation Martensitic Steels” Peer-reviewed

    R. Kasada, A. Kimura

    Jupiter Workshop on Ferritic Steels, Kyoto University, (1999) Dec.1-2 1999

  210. 「Ni添加した低放射化マルテンサイト鋼の異常照射硬化(2)」 Peer-reviewed

    笠田竜太, 松井秀樹, 木村晃彦

    日本金属学会春季大会,1998年3月26-28日. 1998

  211. 「フェライト鋼の照射効果に及ぼす温度変動の影響」 Peer-reviewed

    木村晃彦, 笠田竜太, 松井秀樹

    核融合科学研究所研究会,核融合材料の温度変動照射効果およびデザインウィンドウ評価のための実環境材料照射挙動モデル開発研究会,1998年,2月26-27日. 1998

  212. “Current Status of RAF Steels R&D in Japan” Peer-reviewed

    A. Kimura, R. Kasada

    Jupiter Workshop on Fusion Materials, U of Tokyo, Oct. 27, (1998) 1998

  213. “Factors Controlling Kinetics of Hydrogen Embrittlement of Intermetallic Compounds” Peer-reviewed

    A. Kimura, R. Kasada, M. Yamamoto, T. Morimura, A. Koya

    Proc. of ECOMAP’98, 347-350 (1998) 1998

  214. “Assessment of Helium Embrittlement of Reduced-Activation 9Cr Martensitic Steels” Peer-reviewed

    R. Kasada, A. Kimura, T. Morimura, A. Hasegawa

    Proc. of ECOMAP’98, 625-628 (1998) 1998

  215. 「低放射化マルテンサイト鋼の耐ヘリウム脆化特性」 Peer-reviewed

    木村晃彦, 笠田竜太, 森村太郎, 長谷川晃, 阿部勝憲, 松井秀樹

    プラズマ核融合学会,つくば,1998年12月1-4日 1998

  216. Evaluation of Ductile-Brittle Transition Behavior of Helium-Implanted Reduced Activation 9Cr-2W Martensitic Steel by Small Punch Tests

    Kimura A., Morimura T., Kasada R., Matsui H., Hasegawa A., Abe K.

    CYRIC annual report 1997 49-52 1997

    Publisher: Cyclotron and Radioisotope Center, Tohoku University

  217. “Effects of Irradiation at Low Temperature (below 473 K) on the Mechanical Properties of Reduced Activation Martensitic Steels” Peer-reviewed

    R. Kasada, A. Kimura

    IEA Workshop on Reduced Activation Ferritic/ Martensitic Steels, Tokyo, Nov. 3-4, (1997) 1997

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Books and Other Publications 2

  1. 機動戦士ガンダム 宇宙世紀vs.現代科学

    伊藤篤史, 笠田竜太, 金子俊郎, 福田努, 小池耕彦, 坂本貴和子

    マイナビ出版 2022/03/28

    ISBN: 4839975043

  2. 図解でよくわかる 核融合エネルギーのきほん: 世界が変わる夢のエネルギーのしくみから、環境・ビジネス・教育との関わりや将来像まで

    核融合エネルギーのきほん, 出版委員会, 小川雄一, 岡野邦彦, 笠田竜太

    誠文堂新光社 2021/01/12

Presentations 31

  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の展開 Invited

    笠田竜太, 近藤創介, 藪内聖皓, 檜木達也

    第38回プラズマ・核融合学会年会 2021/11/23

  2. 核データ分野と原子力材料分野の協働の可能性 Invited

    笠田竜太

    日本原子力学会シグマ調査専門委員会 2026/01/25

  3. GOI宇宙世紀憲章合金開発 ボクの考えた最強のガンダリウム合金について Invited

    笠田竜太

    GUNDAM OPEN INNOVATION 2021-2025 ~GOI PROJECT REPORT~ 2025/11/19

  4. イオン照射と中性子照射の互換性解析のレビューと今後の展望 Invited

    笠田竜太

    核融合科学研究所 一般共同研究 核融合炉照射研究会 & 日本金属学会 第9分野 材料照射研究会 2025/10/24

  5. 原子力材料工学の脱構築に向けた研究動向分析 Invited

    笠田竜太

    日本金属学会2025年秋期講演大会 2025/09/18

  6. Q:核融合炉は材料が無いから出来ないって本当ですか? Invited

    笠田竜太

    プラズマ核融合夏の学校 2025/07/29

  7. Irradiation3.0: A Next-Generation Irradiation Concept to Accelerate the Realization of Advanced Nuclear Fission and Fusion Energy and to Pioneer High-Flux Material Science Invited

    Ryuta Kasada

  8. Investigation of local mechanical properties and microstructure of under-clad hardened layer of RPV steel Invited

    Ryuta Kasada, Takashi Noro, Minako Endo, Yuki Jimba, Kaito Kamiyama, Diancheng Geng, Hao Yu, Yasuyuki Ogino, Sosuke Kondo, Hideki Yuya

    Numat2024

  9. Development of Ultra-Small Testing Technologies towards prediction of bulk-scale mechanical properties from local measurements on ion-irradiated materials Invited

    R. Kasada, Y. Furukawa, X. Wu, D. Geng, Y. Jimba, H. Yu, Y. Ogino, S. Kondo

    CJS-15

  10. ビッカース硬さ 100年 Invited

    笠田竜太

    第299回材料試験技術シンポジウム 2024/08/02

  11. Investigation of local mechanical properties and microstructure of under-clad hardened layer of RPV steel

    R. Kasada, T. Noro, H. Yu, D. Geng, S. Kondo, M. Endo, H. Yuya

    The 23rd meeting of the International Group on Radiation Damage Mechanisms in Pressure Vessel Steels (IGRDM23)

  12. Correlation of Vickers hardness and instrumented indentation hardness in Fe-Cr alloys

    Ryuta Kasada, Diancheng Geng, Sosuke Kondo, Hao Yu

    7th International Indentation Workshop (IIW-7)

  13. 先進核融合炉への適⽤に向けたAl添加⾼MnオーステナイトODS鋼の開発

    笠田竜太

    プラズマ・核融合学会第40会年会 2023/11/27

  14. Evaluation of Mechanical Properties of Micro-Scale Features in Reduced-Activation Ferritic Steels using Ultra-Small Testing Technologies Invited

    Ryuta Kasada

    21th International Conference on Fusion Reactor Materials (ICFRM-21)

  15. 金属体験学習の実施例と課題〜研究者と科学技術コミュニケーターの視点から〜 Invited

    笠田 竜太, 冨松 美沙

    日本金属学会2023年秋期大会発表 2023/09/20

  16. Development of ODS alloys for advanced fission and fusion reactors Invited

    8th Korea-Japan Joint Workshop on Fuel & Material Issues fo Advanced Nuclear System 2023/05/17

  17. IIT:計装化押込み試験とビッカース硬さ 100 年 Invited

    笠田竜太

    日本材料試験技術協会第17回 材料試験ユーザーズセミナー 2023/04/27

  18. 核融合炉に求められる耐熱材料

    笠田竜太

    日本学術振興会耐熱金属材料第123委員会第30回討論会 2022/11/07

  19. 核融合炉への適用に向けた酸化物分散強化銅合金の創製

    笠田竜太

    日本銅学会第62回講演大会 2022/10/16

  20. FeCrAlZr-ODS鋼を応用した先進核融合機器の開発に関する研究 (6)液体金属環境への適用に向けたAl含有高MnオーステナイトODS鋼の開発

    笠田 竜太, Haoran Wang, Jiarui Liu, Hao Yu, 近藤 創介, 奥野 泰希, 大久保 成彰, 徳永 透子, 大野 直子

    日本原子力学会2021年春の年会 2021/03/18

  21. 電子線照射A533B鋼の降伏応力に及ぼすマイクロピラーサイズの影響

    笠田 竜太, 鄭 宇暘, 近藤 創介, 余 浩, 木村 晃彦, 熊野 秀樹

    日本金属学会2021春期大会 2021/03/19

  22. Japanese R&D on ODS-Cu for divertor application Invited

    Ryuta Kasada, Hao Yu, Sosuke Kondo, Yuchen Liu, Mohamad Aghamiri, Naoko Oono, Shigeharu Ukai, Hiroyuki Noto, Yoshimitsu Hishinuma, Takeo Muroga

    19th International Conference on Fusion Reactor Materials (ICFRM-19) 2019/10/28

  23. Materials in the Divertor and Blanket International-presentation Invited

    KASADA Ryuta

    US/JA Workshop on Fusion Power Plants, Next Steps and Fusion Technologies 2018/12/14

  24. Action Plan and Roadmap of Japan Fusion Activities International-presentation Invited

    KASADA Ryuta

    US/JA Workshop on Fusion Power Plants, Next Steps and Fusion Technologies 2018/12/13

  25. EPMA-SXESによるホウ素化合物 およびベリリウム合金の分析 ~原子力・核融合材料への応用~ Invited

    笠田 竜太

    2018 JEOL SXESスクール 2018/11/30

  26. Electronic Structure of the Beryllides International-presentation

    KASADA Ryuta

    18th International Symposium on Fusion Reactor Materials (ICFRM-18) 2018/11/10

  27. Indentation hardness of ion-irradiated materials Revisited International-presentation

    KASADA Ryuta

    6th International Indentation Workshop 2018/07/03

  28. Micro-Scale Deformation and Strength of Irradiated Materials International-presentation Invited

    KASADA Ryuta

    The future of Nuclear Materials Research 2018/05/24

  29. REDOX反応制御MA法によるODS-Cu合金の創製

    笠田 竜太, 八尾 栄彰, 小西 哲之, Mohammad Aghamiri, 大野 直子, 鵜飼 重治, 能登 裕之, 菱沼 良光, 室賀 健夫

    日本原子力学会2018年春の年会 2018/03/28

  30. マイクロピラー圧縮試験とナノインデンテーション硬さ試験によるイオン照射硬化評

    笠田 竜太, 志村 力, 小西 哲之, 安堂 正巳, 谷川 博康

    日本金属学会2018年春期大会 2018/03/20

  31. Evaluation of Mechanical Properties of Ion-Irradiated F82H by Micro-Pillar Compression Test and Nanoindentation Hardness Test International-presentation Invited

    KASADA Ryuta

    18th International Symposium on Fusion Reactor Materials (ICFRM-18) 2017/11/10

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Industrial Property Rights 7

  1. 焼結体および焼結方法

    笠田竜太, 近藤創介, 余浩, 陣場優貴

    特許7319000

    Property Type: Patent

    Holder: 国立大学法人東北大学

  2. Cu合金及びCu合金の製造方法

    笠田 竜太, コウ シモク, 余 浩, 近藤 創介, 荻野 靖之

    Property Type: Patent

    Holder: 国立大学法人東北大学

  3. 液滴製造用ノズル、液滴製造装置、核融合装置、および液滴製造方法

    興野文人, 笠田竜太, 小西哲之

    Property Type: Patent

  4. 熱分離方法、熱の回収方法、気体および熱の分離方法、気体および熱の分離回収方法、熱分離装置、気体および熱分離装置、気体および熱分離回収装置、ならびに核融合装置

    興野文人, 笠田竜太, 小西哲之

    Property Type: Patent

  5. ガス化反応装置

    小西哲之, 笠田竜太

    Property Type: Patent

  6. スーパーODS鋼

    木村晃彦, 笠田竜太

    Property Type: Patent

  7. 鋼又はフェライト鋼中の窒素同位体濃縮による放射性核種の低減方法

    林孝夫, 沢井友次, 笠田竜太

    Property Type: Patent

Show all Show first 5

Research Projects 17

  1. 小型モジュール炉における圧力容器鋼の中性子照射脆化評価に向けたデータ同化可能なマルチスケール計算科学手法の開発

    Offer Organization: 文部科学省

    System: 国会課題対応型研究開発推進事業原子力システム研究開発事業

    Category: 一般課題型(異分野連携)

    2025 - 2028/03

  2. FeCrAl-ODSの鉛冷却SMRにおける応力-腐食重畳 環境下の構造健全性工学

    大野直子, 近藤正聡, 笠田竜太

    Category: 基盤研究(B)

    Institution: 横浜国立大学

    2023/04 - 2026/03

  3. 照射脆化耐性を向上する析出相強靭化法の開発とローカルアプローチによるモデル化

    笠田 竜太, 近藤 創介, 余 浩, 大畑 充, 松川 義孝

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 基盤研究(B)

    Institution: 東北大学

    2023/04 - 2026/03

  4. Structural integrity engineering of FeCrAl-ODS in lead-cooled SMR under superimposed stress-corrosion environment

    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: Yokohama National University

    2023/04 - 2026/03

  5. 高放射線耐性の低照度用太陽電池を利用した放射線場マッピング観測システム開発

    System: 英知を結集した原子力科学技術・人材育成推進事業

    Category: 令和4年度課題解決型廃炉研究プログラム

    2022/04 - 2025/03

  6. 原子炉圧力容器鋼クラッド熱影響部における局所力学特性に関する研究

    Offer Organization: 中部電力

    System: 原子力に係る公募研究

    2022/04 - 2024/03

  7. 粒子線照射したタングステンの水素添加による機械的特性変化の評価とメカニズム解明

    佐藤 紘一, 笠田 竜太, 畠山 賢彦, 徐 ぎゅう

    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: 鹿児島大学

    2021/04 - 2024/03

    More details Close

    本研究では、水素添加によるタングステンの機械的特性変化のメカニズム解明を試みるとともに、原型炉ダイバータの設計に資するデータの取得を目指すことを目的とする。そのため、以下4点について調査する。 (1) 電子線照射したタングステンの機械的特性が固溶水素濃度(照射欠陥が捕獲する水素数の変化)に応じて変化することを示し、そのメカニズムを明らかにすること (2) 様々な条件でイオン照射と水素チャージを実施し、温度に勾配があるダイバータ内部の環境を幅広く模擬して、機械的特性変化を得ること (3) 表面硬さだけでなく様々な試験法(引張試験と圧縮試験)を用い、試験法によらず機械的特性変化の傾向が普遍的なものであることを示すこと (4) ダイバータの中で強度特性が水素によって最も変化する部分を特定すること (1)については、タングステンに対して電子線照射を行うことができたが、それ以外の硬さ試験などの実験を実施することができていない。(2)については、573Kでイオン照射した単結晶タングステンに水素チャージをすることで、硬くなる傾向が得られた。原子空孔集合体は塑性変形によって発生する転位の移動を阻害するが、水素を捕獲することによってより強くその移動を阻害したためであると考えられる。また、773Kと1023Kでのイオン照射も実施することができた。(3)についてはマイクロピラー圧縮試験を実施したが、イオンの加速エネルギーが低く、形成する照射層が浅すぎたため、良い結果を得ることができなかった。今後、加速エネルギーを検討する必要がある。また、マイクロ引張試験も行ったが、試験数が少ない状況である。今後、マイクロ引張試験の試験数の増加を目指す。

  8. 革新的精製技術が駆動する有限鉱物資源循環システム共創拠点

    Offer Organization: 科学技術振興機構

    System: 共創の場形成支援プログラム

    Category: 育成型

    2021/01 - 2022/03

  9. 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 Grant-in-Aid for Scientific Research (B)

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Tohoku University

    2019/04 - 2022/03

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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.

  10. 超微小試験技術による原子炉圧力容器鋼の局所力学特性分布特性評価

    Offer Organization: 中部電力

    System: 原子力に係る公募研究

    2019/05 - 2021/03

  11. Creation of radiation-resistant copper alloys for application to divertors Competitive

    Muroga Takeo

    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: National Institute for Fusion Science

    2016/04 - 2020/03

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    The production process of oxide dispersion strengthened (ODS) copper alloys, by means of mechanical alloying (MA) and the following sintering, was investigated for application to divertors of fusion reactors, including water-cooled MA, REDOX-MA, and powder classification by their size after MA. The relation between the enhancement of strength and ductility of the materials produced, and their microstructural parameters was clarified, including the case when post-sintering thermal and mechanical treatments were applied. In addition, high irradiation resistance of the materials produced was demonstrated by means of ion irradiation and nano-indentation. Based on these results, the potential of the ODS copper alloys as divertor heat sink materials was evaluated, and the guidelines for optimizing the production process were extracted.

  12. Development of DEMO-grade irradiation-resistant copper alloy with meso-heterogeneous nano-composite microstructure

    KASADA RYUTA, KONISHI Satoshi, IHIRA Ryota

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Challenging Exploratory Research

    Category: Grant-in-Aid for Challenging Exploratory Research

    Institution: Kyoto University

    2015/04/01 - 2017/03/31

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    In order to elucidate the mechanism of simultaneously improving the strength and ductility of Cu subjected to cryogenic rolling and to clarify the applicability of the cryogenic rolling to CuCrZr alloy for improvement of strength properties and irradiation resistance of Cu base material, we investigated microstructure, tensile properties and neutron irradiation effect. In the CuCrZr alloy, heterogenious crystal grain shown in Cu and a following remarkable simultaneous improvement phenomenon of strength and ductility was not obtained, but a brass type texture different from that of room temperature rolling with good ductility was obtained. In addition, it was shown that water-cooling mechanical alloying method can be applied to Cu alloy as basic experiment of new MA process for development of ODS - Cu alloy having nanocomposite structure.

  13. Dynamic fracture toughness of tungsten under ternary loading

    Lee Heun Tae, UEDA Yoshio, KATSUMA Hiroyuki, YAKUSHIJI Kouki, UEDA Kazuki, ANDO Sousuke, KASADA Ryuta, Thomas Schwarz-Selinger

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Young Scientists (B)

    Institution: Osaka University

    2014/04/01 - 2017/03/31

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    Magnetic nuclear fusion reaction occurs in a plasma confined inside a vacuum vessel with a wall composed of plasma facing material. Tungsten is an important facing material. Tungsten is a brittle material, but in a fusion reactor it is exposed to hydrogen, helium, and neutron particles. These three types of particles are known to increase the brittleness of metals such as tungsten. In this study, the effect of hydrogen, helium, and neutrons on the mechanical behavior of tungsten was clarified. We also examined select cases of binary and ternary loading. The mechanical properties of tungsten were evaluated by applying a new experimental method called laser ultrasonic method. We also evaluated the mechanical properties of advanced materials to overcome brittle fracture of tungsten.

  14. High heat flux energy transport phenomena in hyper thermal conductivity divertor

    KONISHI Satoshi, YAMAMOTO Yasusi, KASADA Ryuta, NOBORIO Kazuyuki

    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

    2013/04/01 - 2016/03/31

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    This study intends to propose and verify a new concept of fusion divertor that utilizes energy by extremely large heat transport capability. The divertor device investigated in this research receives high heat and particle flux on tungsten armor covering thin copper target material, followed by heat transport in small temperature gradient as latent heat by heat pipe mechanism, that was fond to be optimum. This feature was found to be subject to the repeated pulses by plasma mode named ELM, and the test was performed with YAG laser to simulate this effect. The heat transport performance was proved to be affected little by this heat pulses, and the concept of this divertor was verified to effectively convert fusion energy from plasma and provide it for the power train for electricity generation.

  15. challenge to evaluation of irradiation hardening without hardness tests by nanoindentation method

    KASADA Ryuta

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research Grant-in-Aid for Challenging Exploratory Research

    Category: Grant-in-Aid for Challenging Exploratory Research

    Institution: Kyoto University

    2013/04/01 - 2015/03/31

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    This is an experimental study which aims to evaluate irradiation hardening not by hardness but directly by nanoindentation. As a main achievement, micro-pillar compression test method was examined to evaluate mechanical properties of the ion-irradiated material. Also, the pop-in phenomenon of a single crystal material by nanoindetation was investigated to reveal ion-irradiation effect on the critical shear stress. In addition, a new analysis method for nanoindentation hardness test on ion-irradiated materials were propesed.

  16. 高経年化原子炉圧力容器鋼の照射硬化におけるマンガン影響の抽出

    笠田 竜太

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 若手研究(B)

    Category: 若手研究(B)

    Institution: 京都大学

    2006 - 2007

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    原子炉圧力容器(RPV)鋼の照射脆化の評価・予測の高度化・高精度化に貢献するために、低銅含有RPV鋼及び鉄基モデル合金の照射硬化挙動やマトリックス損傷形成過程に及ぼすマンガン、ニッケル、クロム、モリブデン等の合金元素の影響について調べた。イオン加速器システムDuETを用いて鉄イオン照射した鉄基二元系モデル合金とRPV鋼(A533B)の照射硬化挙動を詳細に調べ、照射硬化の飽和挙動に対して合金元素の種類と添加量が大きな影響を及ぼすことが明らかになった。特に、鉄基二元系モデル合金におけるマンガンとニッケルは、照射硬化の飽和量を鉄-銅二元型モデル合金以上に増加させるとともに、0.1dpa程度で飽和する鉄-銅合金と異なり、飽和までより高い照射量(1dpa以上)を必要とすることが示された。また、鉄-マンガン二元系合金における照射硬化の飽和挙動が純鉄等と著しく異なる理由として、モデル合金の照射硬化の主要因であるマトリックス損傷(この場合、微小な転位ループ)の核形成が、マンガン原子による点欠陥捕獲によって促進されているためであると示唆される。昨年度に得られたイオン照射研究におけるA533B鋼の照射硬化の照射量依存性はFe-1.5Mn合金のそれとよく一致していることからA533B鋼におけるMn影響が示唆されたが、今年度実施したFE-TEMによる微細組織観察によって、両材料において微細な転位ループが形成していることを確認することが出来た。これらの結果より、今後は、実機環境に近い損傷速度条件において、マトリックス損傷形態に及ぼすマンガン影響或いはニッケル影響を詳細に調べることが、高経年化低銅含有RPV鋼の照射硬化・脆化機構を明らかにする上で重要であることを提言する。

  17. 核融合炉材料中の照射誘起ナノスケール欠陥クラスターによる硬化挙動の微視的評価

    笠田 竜太

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業 若手研究(B)

    Category: 若手研究(B)

    Institution: 京都大学

    2002 - 2003

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    核融合炉材料の照射硬化の原因となる照射誘起欠陥と運動転位の動的相互作用の直接観察による硬化因子の同定および硬化量の定量的評価手法の確立を目的として,従来用いられてきた手法を遥かに上回る精密さを期待できる下記の手法を検討し確立した. 高エネルギー粒子線照射設備として,京都大学エネルギー理工学研究所設置の高度エネルギー機能変換実験装置/材料実験装置(DuET)を使用した.DuETでは照射温度や損傷速度を広範囲で変化させることができるため,照射誘起欠陥の種類や分布を選択的に得ることが可能となった. TEM内引張その場観察試験用試料の作成に関しては,デュアルイオン(Fe^<3+>およびHe^+)照射した試料に対して,収束イオンビーム加工観察装置(FIB)による手法を検討するとともに電解研磨法の高度化により確立した.その場観察の録画に関しては,既存の設備であるハイビジョンCCDカメラを有効に利用し,民生用デジタルビデオ技術を採用することにより安価に構築することに成功した. 本手法によるモデル研究として,酸化物分散強化(ODS)フェライト鋼中のイットリア分散粒子と運動転位の相互作用のTEM内引張その場観察を行い,分散粒子による転位の強いピン止め効果を直接確認することができた.照射誘起欠陥集合体(転位ループやキャビティ)の形成による照射硬化現象は,分散強化もしくは析出強化のモデルを応用して説明されているため,分散強化で確立した評価手法は,照射硬化の評価にも有効であると考えられる. 本研究で確立された手法は,核融合炉材料の経年劣化評価あるいは予測を行う上で,有用な知見を提供するものである.

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Teaching Experience 14

  1. Special Lecture on Nuclear Materials Engineering Tohoku University

  2. Material Science Tohoku University

  3. 材料科学A 東北大学工学部機械知能・航空工学科

  4. Introduction to quantumn energy science Tohoku University

  5. 機械工学序説 東北大学

  6. 核燃料・材料学概論 東北大学工学部機械知能・航空工学科

  7. Nuclear energy system and material Tohoku University, Graduate School of Engineering, Department of Quantum Science and Energy Engineering

  8. Radiation Materials Science Sichuan University

  9. Special lecture on energy materials Tohoku University

  10. Module 4 Hokkaido University Other

  11. Material Science I Tohoku University, Faculty of Engineering, Department of Mechanical and Aerospace Engineering

  12. 材料科学の最前線 東北大学 Undergraduate (liberal arts)

  13. Material Science II Tohoku University, Faculty of Engineering, Department of Mechanical and Aerospace Engineering

  14. Interactive short course Tohoku University

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Social Activities 20

  1. 硬さで探る!原子炉圧力容器の健全性

    ちゅうでんサイエンス・フォーラム2024

    2024/08/24 - 2024/08/24

  2. 核融合エネルギーの実現に向けて~材料工学からのアプローチ

    大学学部研究会

    2024/08/06 - 2024/08/15

  3. 静岡県立清水東高校見学受入

    2024/08/09 - 2024/08/09

  4. 大和町立落合小学校における出前授業

    楽しい理科のはなし2024不思議の箱を開けよう

    2024/07/03 - 2024/07/03

  5. 多賀城市立高崎中学校見学受入

    2024/07/02 - 2024/07/02

  6. みやぎ県民大学「持続可能な未来社会を創る材料の科学と技術」

    みやぎ県民大学

    2024/06/26 - 2024/06/26

  7. OITA SPACE HIKE 2023 パネルディスカッション

    OITA SPCE HIKE 2023

    2023/09/17 - 2023/09/18

  8. 核融合の実現を見据える。“地味でも大事な”構造材料の話

    ニュースイッチ

    2023/01/02 - 2023/01/02

  9. ワークショップ「モノのカタサと温度を測ろう」

    楽しい理科のはなし2025 ~不思議の箱を開けよう~

    2026/03/07 -

  10. 核融合炉を形にするー工学の挑戦

    Fusion Science School 2025「フュージョン発電所の作り方~未来をデザインする三日間~」

    2026/01/30 -

  11. 片平まつり 金研一般公開 実行委員長

    片平まつり 金研一般公開

    2025/10/11 -

  12. 岩手県立水沢高校見学受入

    水沢高校研究室見学

    2025/08/21 -

  13. 大和町立吉田小学校における出前授業

    楽しい理科のはなし2025

    2025/07/11 -

  14. モノがカタイってどういうこと?(鶴谷東小学校)

    楽しい理科のはなし2024不思議の箱を開けよう

    2024/01/17 -

  15. 核融合炉の研究開発の最新動向と構造材料の要求特性・課題・開発動向

    オンライン配信セミナー

    2023/12/12 -

  16. 原発 長期運転 40年超稼働 世界的な潮流

    読売新聞 読売新聞オンライン

    2023/09/22 -

  17. セミナー「高融点ホウ化物の特性を下げることなく低温焼結を可能にする新助剤の開発」

    セミナー「セラミックス焼成プロセスの省エネ化とシミュレーション技術」

    2023/06/29 -

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    第2部 高融点ホウ化物の特性を下げることなく低温焼結を可能にする新助剤の開発

  18. 研究とは何か

    2023/04/18 -

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    国際・理数探求科2年生を対象とする講義を実施

  19. 対面講義「未来のテクノロジーの実現を考えよう」

    工学部オープンキャンパス 東北大学工学部サイエンスキャンパスホール

    2022/07/27 -

  20. ガンダムと核融合炉からひもとく材料科学

    土曜講座

    2022/06/18 -

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Media Coverage 2

  1. 未来のエネルギーとしての核融合 早期の社会実装への人材育成が重要に

    学校法人 先端教育機構 出版部 月刊 先端教育 28ページ

    2026/02

    Type: Newspaper, magazine

  2. 核融合炉に適用へ。高強度で高伝導の銅合金を東北大が開発

    日刊工業新聞

    2022/01/05

    Type: Newspaper, magazine

Academic Activities 7

  1. 日本材料試験技術協会理事

    2025/04 - Present

  2. 日本原子力学会材料部会副部会長

    2025/04 - 2026/03

    Activity type: Academic society, research group, etc.

  3. 日本金属学会シンポジウム「タングステン材料科学」の主催

    仙台国際センター

    2022/12/08 - 2022/12/09

    Activity type: Academic society, research group, etc.

  4. 材料照射研究会2022「Irradiation3.0に向けて」の主催

    仙台国際センター

    2022/12/07 - 2022/12/09

    Activity type: Academic society, research group, etc.

  5. 第14回核融合エネルギー連合講演会プログラム委員長兼実行委員長

    2022/07/07 - 2022/07/08

    Activity type: Competition, symposium, etc.

  6. 第13回核融合エネルギー連合講演会プログラム委員長

    2020/06/11 - 2020/06/12

  7. 第22回核融合炉材料国際会議(ICFRM22)国際諮問委員、出版委員長

    2025/10 -

    Activity type: Competition, symposium, etc.

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