Published April 2002
| Version v1
Journal article
Introduction of DRM for large break LOCA analysis
Description
From the developing of Large Break LOCA analysis method, the author introduces the French DRM (Deterministic Realistic Methodology) used for Large Break LOCA. The DRM which is a effective industrial tool for NPP safety evaluation, fuel management optimized and economic benefit enhanced of nuclear power plant may be developed important affect. The DRM has been used for justification of increasing core power factor in Daya Bay NPS 18-month fuel cycle project
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 23
- Journal Issue
- 2
- Journal Page Range
- p. 42-45
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 34022716
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- C CODES; DAYA BAY-1 REACTOR; DAYA BAY-2 REACTOR; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; SAFETY ANALYSIS; STATISTICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; MATHEMATICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS