Multiple aspects of raw data collection and processing for Romanian TRIGA SSR Original Research Article

Probabilistic Safety Assessment (PSA) is a tool for evaluating and enhancing the safety of a nuclear reactor. In general, PSA is used to support the system design, configuration decisions and the operational safety management of the plant. Ideally, failure data used for safety and reliability analyses should be based on site-specific data. The paper presents activities and results that started in 2001 with the participation of Romanian TRIGA Steady State 14 MW reactor in an international project for expanding component reliability database for Research Reactors for PSA use. Collection of reliability data for Romanian TRIGA is discussed emphasizing the problems encountered. Failure data for some components is given, both stand-alone and in comparison with other research reactors, as well as statistics pertaining to the failures and failure modes of the investigated components. A brief presentation of a software application developed in the Institute for Nuclear Research (INR) for raw data acquisition and processing is included.