Published 2002 | Version v1
Book

BWR 9 X 9 Fuel Assembly Thermal-Hydraulic Tests (1): New Formula for Post Boiling Transition Heat Transfer Correlation and Re-wet Correlation

  • 1. Nuclear Power Engineering Corporation, 17-1 Toranomon 3-chome, Minato-ku, Tokyo 105-0001 (Japan)
  • 2. Toshiba Corporation (Japan)
  • 3. Global Nuclear Fuel-Japan Co., Ltd., Tokyo (Japan)
  • 4. Nuclear Fuel Industries Ltd. (Japan)

Description

Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8 x 8 and 9 x 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 x 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 re-wet correlations for the estimation of fuel rod surface temperature. (authors)

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
Imprint Pagination
13 p.

Conference

Title
10. international conference on nuclear engineering
Acronym
ICONE-10
Dates
14-18 Apr 2002
Place
Arlington - Virginia (United States)