Published July 1989 | Version v1
Report Open

Application of probabilistic safety assessment to research reactors

Description

This document has been prepared to assist in the performance of a research reactor probabilistic safety assessment (PSA). It offers examples of experience gained by a number of Member States in carrying out PSA for research reactors. These examples are illustrative of the types of approach adopted, the problems that arise and the judgements entered into when conducting a PSA. The illustrative examples of experiences gained are discussed in a series of thirteen chapters which address some of the issues that arise in a PSA. The examples are not exhaustive and offer evidence of how other analyses have approached the task of preparing a PSA, for their particular plant. The principles should be capable of being utilised and the various issues which are discussed should be translated into the needs of the analyst. Each PSA will make its own demands on the analyst depending on the reactor and so the illustrations must only be used as guidance and not adopted as published, without critical appreciation. Refs, figs and tabs

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Subtitle (English)
Report prepared within the framework of an International Atomic Energy Agency Co-ordinated Research Programme

Publishing Information

Imprint Pagination
87 p.
Report number
IAEA-TECDOC--517

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
21003309
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
FAILURE MODE ANALYSIS; HUMAN FACTORS; IAEA; PROBABILISTIC ESTIMATION; RECOMMENDATIONS; RESEARCH REACTORS; SAFETY ANALYSIS
Descriptors DEC
INTERNATIONAL ORGANIZATIONS; REACTORS; RESEARCH AND TEST REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS