WEKO3
アイテム
The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO in-vessel components
https://repo.qst.go.jp/records/84783
https://repo.qst.go.jp/records/84783a94c8723-3613-4468-9956-6cc0dce3ff08
Item type | 学術雑誌論文 / Journal Article(1) | |||||
---|---|---|---|---|---|---|
公開日 | 2021-10-14 | |||||
タイトル | ||||||
タイトル | The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO in-vessel components | |||||
言語 | ||||||
言語 | eng | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | journal article | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Nozawa, Takashi
× Nozawa, Takashi× Tanigawa, Hiroyasu× Kojima, Takaki× Itoh, Takamoto× Hiyoshi, Noritake× Ohata, Mitsuru× Kato, Taichiro× Ando, Masami× Nakajima, Motoki× Hirose, Takanori× D. Reed, Jordan× Chen, Xiang× W. Geringer, Josina× Katoh, Yutai× Takashi, Nozawa× Hiroyasu, Tanigawa× Taichiro, Kato× Masami, Ando× Motoki, Nakajima× Takanori, Hirose |
|||||
抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | This paper summarizes the current status of the material properties handbook for a structural design using Japanese reduced-activation ferritic/martensitic steel F82H. Specifically, the key structural parameters, e.g. time-independent/dependent design stresses and fatigue design curves, were determined by following the French structural design code RCC-MRx. Moreover, under the Japan–U.S. collaboration, tensile data were newly added to the benchmark heavy irradiation data up to 80 dpa, as critical input information in the intermediate check and review in Japan. Furthermore, the status of structural material data and the near-term and long-term issues were clarified by the evaluation using the attribute guides. In parallel, the structural design approaches, which were newly introduced and extended to cope with the structural design issues under the complex environmental conditions peculiar to the DEMO reactor, were noted with the initial R&D results. Of the many design issues, the multi-axial loading conditions due to the complexity of the DEMO reactor as well as the coolant compatibility and the irradiation effect are mentioned. For example, in the paper, multi-axial fatigue–creep testing and evaluation using the modified universal slope method and brittle/ductile fracture testing and evaluation using the local approach are explained toward DEMO. | |||||
書誌情報 |
Nuclear Fusion 巻 61, p. 116054, 発行日 2021-10 |
|||||
出版者 | ||||||
出版者 | IOP Publishing | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0029-5515 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1088/1741-4326/ac269f | |||||
関連サイト | ||||||
識別子タイプ | URI | |||||
関連識別子 | https://iopscience.iop.org/article/10.1088/1741-4326/ac269f/meta |