Published 1990
| Version v1
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Application of phenomenological calculations to the N Reactor probabilistic risk assessment
Description
A deterministic phenomenological calculation generates only a single best estimate result. However, probabilistic risk assessment (PRA) accident progression calculations require phenomenological data in the form of probability distributions. A three step process, to provide such distributions, consisting of issue identification, deterministic calculation specification, and the use of expert judgment to interpret the results, is described in this paper. The results of a sample expert judgment elicitation from the N Reactor PRA are included to demonstrate how the uncertainties associated with deterministic calculations are accounted for in the final probability distributions that are based on those calculations. 6 refs., 2 figs., 3 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 - OSTI as DE90015166; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- SAND--90-0113C
Conference
- Title
- American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities.
- Dates
- 30 Sep - 3 Oct 1990.
- Place
- Boise, ID (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21090627
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL REACTIONS; CONTAINMENT; ECCS; FUEL ELEMENTS; H CODES; HYDROGEN; M CODES; N-REACTOR; PROBABILITY; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ELEMENTS; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; NONMETALS; PLUTONIUM PRODUCTION REACTORS; POWER REACTORS; PRODUCTION REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Secondary number(s)
- CONF-900917--11.