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Technical Basis of Accident Tolerant Fuel Updated Under a Japanese R&D Project
https://repo.qst.go.jp/records/54811
https://repo.qst.go.jp/records/548119e7d7a2a-368f-4a6a-80fd-c03f6330602c
| Item type | 会議発表論文 / Conference Paper(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-11-14 | |||||
| タイトル | ||||||
| タイトル | Technical Basis of Accident Tolerant Fuel Updated Under a Japanese R&D Project | |||||
| 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_5794 | |||||
| 資源タイプ | conference paper | |||||
| 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 |
Yamashita, Shinichiro
× Yamashita, Shinichiro× Nagase, Fumihisa× Kurata, Masaki× Nozawa, Takashi× Watanabe, Seiichi× Kirimura, Kazuki× Kakiuchi, Kazuo× Kondo, Takao× Sakamoto, Kan× Kusagaya, Kazuyuki× Ukai, Shigeharu× Kimura, Akihiko× 野澤 貴史 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | In Japan, the research and development (R&D) project on accident tolerant fuel and other components (ATFs) of light water reactors (LWRs) has been initiated in 2015 for establishing technical basis of ATFs. The Japan Atomic Energy Agency (JAEA) has coordinated and carried out this ATF R&D project in cooperation with power plant providers, fuel venders and universities for making the best use of the experiences, knowledges in commercial uses of zirconium-base alloys (Zircaloy) in LWRs. ATF candidate materials under consideration in the project are FeCrAl steel strengthened by dispersion of fine oxide particles (FeCrAl-ODS) and silicon carbide (SiC) composite, and are expecting to endure severe accident conditions in the reactor core for a longer period of time than the Zircaloy while maintaining or improving fuel performance during normal operations. In this paper, the experimental and analytical data were updated and subsequently the “knowledge gap” to the achievement of practical use was narrowed down by using the technology readiness level (TRL) tables and the attribute guides. | |||||
| 書誌情報 |
Proceedings of 2017 Water Reactor Fuel Performance Meeting 発行日 2017-09 |
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