BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -

Yoshiaki Tsukuda, Hirohisa Kaneko, Nobuaki Abe, Riichiro Suzuki, Hiroshi Hayashi, Toru Mitsutake, Shinichi Morooka, Koujun Isaka, Miyuki Akiba, Yasuhiro Masuhara, Yuji Nishino

研究成果: Conference contribution

抄録

Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8×8 and 9×9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, post boiling transition (post-BT) tests by the use of full-scale test assemblies simulating 9×9 fuel were carried out to evaluate BWR fuel integrity. Two kinds of post-BT tests, the steady-state post-BT test and transient post-BT test were performed, and the test results were applied to development of new heat transfer and rewet correlations for the estimation of fuel rod surface temperature.

本文言語English
ホスト出版物のタイトルInternational Conference on Nuclear Engineering, Proceedings, ICONE
ページ943-955
ページ数13
3
出版ステータスPublished - 2002
外部発表はい
イベント10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA
継続期間: 2002 4 142002 4 18

Other

Other10th International Conference on Nuclear Engineering (ICONE 10)
CityArlington, VA
Period02/4/1402/4/18

ASJC Scopus subject areas

  • エネルギー(全般)
  • 工学(全般)

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