Hello to all,
Nuclear reactor safety technology is based on Deterministic Safety Analysis (DSA) and Probabilistic Safety Analysis (PSA). To perform DSA, properly qualified computational tools are needed. The V&V is the quality demonstration of models and codes in the area of nuclear thermal hydraulics. The V&V process for DSA somehow has a clear path. But recently, I have focused on the qualification process of PSA. It seems that the qualification in PSA is blurry. How the qualification of PSA is performed? How the probabilities and reliability data are qualified?
Still, I am confused in this regard. Do you have any suggestions?
Thank you,
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