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
Creators
- 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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39086200
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; BURNUP; BWR TYPE REACTORS; CORRELATIONS; DESIGN; ECONOMY; ENGINEERING; FUEL ASSEMBLIES; FUEL INTEGRITY; FUEL RODS; HEAT TRANSFER; NUCLEAR POWER; RELIABILITY; STEADY-STATE CONDITIONS; SURFACES; THERMAL HYDRAULICS; TRADE; TRANSIENTS; TRANSITION HEAT
- Descriptors DEC
- ENERGY TRANSFER; ENRICHED URANIUM REACTORS; ENTHALPY; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POWER; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS