Probabilistic safety assessments at EDF
Description
The paper discusses the background of probabilistic studies at Electricite de France; the PSA 1300 project (a probabilistic safety assessment of a standardized 1300 MW pressurized water reactor) including features of the assessment, e.g., level, scope of the assessment, methodological content, basis of French operating experience, and work toward a living assessment; results and lessons to be drawn including risk level, distribution of the risk, and main sequences; and other observations such as shutdown states, the human factor, and contribution of the characteristics in the French safety process; limits of the assessment; and uses in France. The PSA 1300 has now been completed. Some major lessons have been drawn from this assessment while taking account of the identified limits of probabilistic assessment
Additional details
Publishing Information
- Imprint Title
- CSNI workshop on PSA applications and limitations. Proceedings
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. 111-123.
- Report number
- NUREG/CP--0115
Conference
- Title
- Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations.
- Dates
- 4-6 Sep 1990.
- Place
- Santa Fe, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008679
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; AVAILABILITY; BUGEY-5 REACTOR; EDUCATION; EMERGENCY PLANS; FAILURE MODE ANALYSIS; FEEDWATER; FESSENHEIM-1 REACTOR; FRANCE; HUMAN FACTORS; MANAGEMENT; MITIGATION; PALUEL-1 REACTOR; PALUEL-2 REACTOR; PALUEL-3 REACTOR; PALUEL-4 REACTOR; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; PROBABILITY; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR MAINTENANCE; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; RELIABILITY; RISK ASSESSMENT; RUPTURES; SAFETY ENGINEERING; SECONDARY COOLANT CIRCUITS; STANDARDIZATION; STEAM GENERATORS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; FAILURES; HYDROGEN COMPOUNDS; MAINTENANCE; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- SAND--90-2797; CONF-9009346--.