Published 1988 | Version v1
Report Open

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