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.

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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).

Optional Information

Contract/Grant/Project number
Contract AC04-76DP00789
Secondary number(s)
CONF-900917--11.