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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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.

Original languageEnglish
Title of host publicationInternational Conference on Nuclear Engineering, Proceedings, ICONE
Pages943-955
Number of pages13
Volume3
Publication statusPublished - 2002
Externally publishedYes
Event10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA
Duration: 2002 Apr 142002 Apr 18

Other

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

ASJC Scopus subject areas

  • Energy(all)
  • Engineering(all)

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