Published 1983 | Version v1
Report Restricted

Evaluation of the sensitivity of reactor risks to uncertainties

Description

The increase in the use of Probabilistic Risk Assessment (PRA) in the evaluation of nuclear reactor safety has prompted a need for evaluation of the sensitivity of PRA results to specific uncertainties. This paper discusses results from the evaluation of the sensitivity of reactor risks to uncertainty in the in-vessel steam explosion probability, containment failure pressure, source term release magnitudes, site population density, and interdiction dose criterion. These uncertainties are addressed individually; potential synergistic effects are not considered. Examination of the uncertainties should enhance the use of PRA as applied to the evaluation of nuclear reactor safety

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE83016883.

Files

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Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
8 p.
Report number
SAND--83-0855C

Conference

Title
International meeting on light-water reactor severe accident evaluation.
Dates
28 Aug - 1 Sep 1983.
Place
Cambridge, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15002018
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; ECONOMICS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ANALYSIS
Descriptors DEC
ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-830816--32.