Published 1995
| Version v1
Miscellaneous
The BR2 probabilistic safety assessment project
Description
The probabilistic safety assessment (PSA) pointed systematically to the weaknesses of the Belgian Reactor Two (BR2). The PSA did not raise any insoluble problems. The PSA gave an acceptable safety level overall for the plant. Nonetheless, further improvements are still required. The BR2 PSA is proving to be an invaluable decision-making tool towards achieving this. (author)
Additional details
Publishing Information
- Imprint Title
- ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 3
- Imprint Pagination
- 534 p.
- Journal Page Range
- p. 1361-1366
Conference
- Title
- 3. JSME/ASME joint international conference on nuclear engineering
- Acronym
- ICONE-3
- Dates
- 23-27 Apr 1995
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38008915
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BR-2 REACTOR; ERRORS; FAILURE MODE ANALYSIS; HUMAN FACTORS; LOSS OF COOLANT; MODIFICATIONS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RISK ASSESSMENT; SCRAM; VALVES; VULNERABILITY
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 18 refs., 4 figs.