FEMAXI-7 prediction of the behavior of BWR-type accident tolerant fuel rod with FeCrAl-ODS steel cladding in normal condition
山路 哲史*; 山崎 大輝*; 岡田 知也*; 坂本 寛*; 山下 真一郎
Yamaji, Akifumi*; Yamasaki, Daiki*; Okada, Tomoya*; Sakamoto, Kan*; Yamashita, Shinichiro
Features of the accident tolerant fuel performance were evaluated with FEMAXI-7 when the current Zircaloy(Zry) cladding is replaced with FeCrAl-ODS steel cladding (a type of oxide dispersion strengthened steel being developed under the Project on Development of Technical Basis for Safety Improvement at Nuclear Power Plants by Ministry of Economy, Trade and Industry (METI) of Japan) for BWR 9$$times$$9 type fuel rod. In particular, influences of the creep strain rate and thickness of the ODS cladding on the fuel temperature, fission gas release rate (FGR) and pellet-cladding mechanical interaction (PCMI) are investigated.
使用言語 : English
掲載資料名 : Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive)
ページ数 : 10 Pages
発行年月 : 2017/09
出版社名 :
発表会議名 : 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017)
開催年月 : 2017/09
開催都市 : Jeju
開催国 : Korea
特許データ :
論文URL :
キーワード : BWR; Accident Tolerant Fuel; Oxide Dispersion-strengthened; ODS
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 : 経済産業省資源エネルギー庁
登録番号 : BB20170931
抄録集掲載番号 : 45001390
論文投稿番号 : 19616
Accesses  (From Jun. 2, 2014)
- Accesses
Add This