Published April 1979 | Version v1
Report Restricted

Probabilistic safety analysis IV. Final report

Creators

Description

The primary goal of the study has been to continue development of probabilistic risk assessment methodology and its applicability to utility requirements. Improvements have been developed for methods of fault tree analysis, consequence analysis, and ATWS data collection and retrieval. Progress has been documented for an analysis of external fuel cycle risks. A technique has been developed for applying regional seismic histories to analyses of risk from earthquakes

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.

Files

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Additional details

Additional titles

Augmented title (English)
BWR; PWR

Publishing Information

Imprint Pagination
77 p.
Report number
EPRI-NP--1039

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10487475
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ATWS; BWR TYPE REACTORS; EARTHQUAKES; PWR TYPE REACTORS; RISK ANALYSIS; SEISMIC EFFECTS
Descriptors DEC
ACCIDENTS; DESIGN BASIS ACCIDENTS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS