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.Files
21003309.pdf
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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