New Developments in Probabilistic Risk Assessment Methodology for Nuclear Fuel Cycle Facilities

Abstract

Probabilistic Risk Assessment (PRA) originally was developed and employed in nuclear power plant safety analysis. For some years other contributions to the risk of nuclear energy production resulting from nuclear fuel cycle activities, e.g. mining and milling, transportation, reprocessing, storage facilities, and repositories for final disposal were considered to be less important. Rather soon, however, the lack of quantitative evidence and the necessity for appropriate methods and models for PRA in these particular fields have become more and more apparent.