Probabilistic safety assessment of the research reactor - TRIGA Mark II
- 1. Institut 'Jozef Stefan', Jamova 39, Ljubljana (Yugoslavia)
Description
The probabilistic safety analysis method was used to assess a risk level - associated with the research reactor TRIGA MARK II. The model of the reactor is presented by the system event trees for four initiating events. The system fault trees and the critical sequence event trees are reduced by means of the FTAP 2 program, and the quantitative evaluation was done by means of the IMPORT programme. The four initiating events selected were: LOCA, Loss of Electric Supply, Loss of Flow and Loss of flow-fuel Channel Blockage. For all four initiating events, event trees were constructed and the probability for core damage was calculated as well as the probability for the radioactive release. Most critical sequences were identified for each event trees and further analysed giving Importance measures (Im), Risk Reduction Rations (RRW) and Risk Achievement Rations (RAW). At the end, beside giving estimate about the risk level, some suggestions are given based on our results. (author)
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Additional details
Publishing Information
- Imprint Title
- 10. European TRIGA users conference. Papers and abstracts
- Imprint Pagination
- 570 p.
- Journal Page Range
- p. 4.17-4.28
- Report number
- INIS-AT--09N0043
Conference
- Title
- 10. European TRIGA users conference
- Dates
- 14-16 Sep 1988
- Place
- Vienna (Austria)
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40082688
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAULT TREE ANALYSIS; HAZARDS; LOSS OF COOLANT; LOSS OF FLOW; NUCLEAR FUELS; PROBABILISTIC ESTIMATION; RESEARCH REACTORS; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENERGY SOURCES; FUELS; MATERIALS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Lead record
- pe698-57w21
- Notes
- 3 refs, 5 figs
- Secondary number(s)
- TOC--21