INFLUENCE OF SPECIFIC DATA ON A RESEARCH REACTOR PROBABILISTIC MODEL

Deterministic safety calculations are usually required and included in the Safety Analysis Report of research reactors. To estimate the risk of a research reactor, Probabilistic Safety Assessment (PSA) is rarel y used. In this paper, a PSA of a TRIGA Mark II research reactor with generic and specific data is described. The results are discussed to s how the need for PSA and the usefulness of specific examination of the research reactor. Beside the deterministic calculations, PSA has prov ed to be a powerful tool for safety evaluation of the research reactor . It is recommended that as much specific data is used as is possible for initiating event definitions and frequencies estimation. We do not recommend the building of an extensive data base for components. When safety of non-standard technologies is estimated it is recommended th at a preliminary PSA is carried out first. It enables definition of ne eded specific data to be collected and contributes to better employmen t of human resources. (C) 1996 Elsevier Science Limited.