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AbstractAbstract
[en] The probabilistic safety analysis method was used to asses a risk level associated with the research reactor TRIGA MARK II. The model of the research reactor is presented by the system even trees for four initial events. The system fault tree and the critical sequence fault tree are reduced by means of the FTAP 2 programme, and the quantitative treatment by means of the IMPORT programme. (author)
Original Title
Verjetnostna varsnostna analiza raziskovalnega reaktorja TRIGA MARK II
Primary Subject
Source
1988; 8 p; Society for Electronics,Telecommunications, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); 32. Conference - ETRAN '88: Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering; ETAN '88: 32. Konferencija za elektroniku, telekomunikacije, automatiku i nuklearnu tehniku; Sarajevo (Yugoslavia); 6-10 Jun 1988; Also available from the Institute of Nuclear Sciences VINCA; 4 refs., 7 figs., 2 tabs.
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
CALCULATION METHODS, COMPUTER CODES, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
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