Genusa Bepu methodologies for the safety analysis of BWRs
Creators
Description
This article describes the BEPU methodologies developed by General Electric-Hitachi (GEH) for the evaluation of the BWR reactor safety analysis based on the TRACG best-estimate code. These methodologies are applicable to a wide range of events, operational transients (AOO), anticipated transients without scram (ATWS), loss of coolant accidents (LOCA) and instability events; to different BWR types operating commercially. General Electric (GE( designs and other vendors, including Generation III+ESBWR; to the new operation strategies, and to all types of BWR fuel. Their application achieves, among other benefits, a better understanding of the overall plant response and an improvement in margins to the operating limits; thus, the increase of flexibility in reactor operation and reduction in generation costs. (Author)
Additional details
Additional titles
- Original title (Spanish)
- Metodologias Bepu de Genusa para el analisis de seguridad de reactores BWR
Publishing Information
- Journal Title
- Nuclear Espana (1996)
- Journal Volume
- 373
- Journal Page Range
- p. 15-20
- ISSN
- 1137-2885
- CODEN
- NUESFO
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- Spain
- INIS RN
- 47081770
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BWR TYPE REACTORS; COST; DESIGN; FLEXIBILITY; LICENSING REGULATIONS; SAFETY; SAFETY ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; LAWS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; REGULATIONS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 20 refs.