Current Status of the Post Boiling Transition Research in Japan Integrity Evaluation of Nuclear Fuel Assemblies after Boiling Transition and Development of Rewetting Correlations

Takashi Hara, Shinya Mizokami*, Yoshiro Kudo, Seiichi Komura, Yoshifumi Nagata, Shinichi Morooka

*この研究の対応する著者

研究成果: Article査読

14 被引用数 (Scopus)

抄録

Development of rewetting correlation formula was the key to predict fuel-cladding temperature after Boiling Transition (BT). Japanese BWR utilities and vendors performed some tests of rewetting and made two rewetting correlation formulas. The effect on fuel integrity after BT depends on temperature of fuel rod and time of dryout. Main cause of losing fuel integrity during BWR's Anticipated Operational Occurrences (AOO) after BT is embrittlement of the claddings due to oxidation. Ballooning of fuel rod is excepted because its pressure boundary isn't broken. In Japan, the Standards Committee of Atomic Energy Society of Japan (AESJ) is making post BT standard. This standard provides guidelines based on the latest knowledge to judge fuel integrity in case of BT and the validity of reusing the fuel assembly that experienced BT in BWRs.

本文言語English
ページ(範囲)852-861
ページ数10
ジャーナルJournal of Nuclear Science and Technology
40
10
出版ステータスPublished - 2003 10月
外部発表はい

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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