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 rarely 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 show the need for PSA and the usefulness of specific examination of the research reactor. the deterministic calculations, PSA has proved 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 that a preliminary PSA is carried out first. It enables definition of needed specific data to be collected and contributes to better employment of human resources.