Uncertainty Analysis for Unprotected Accidents in Sodium-Cooled Fast Reactors
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概要
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Reactor safety analyses often utilize a deterministic approach where in addition to performing best estimate calculations, uncertainty is accommodated by performing calculations with pessimistic values for input parameters that are important to safety. Here, a stochastic approach is considered for explicitly including uncertainty in safety parameters by applying Monte Carlo sampling coupled with established deterministic reactor safety analysis tools. The Monte Carlo approach yields frequency distributions for reactor safety metrics (e.g., peak temperatures) that can be compared to performance limits, allowing for an improved determination of the safety margin and a clear determination of which safety parameters are most important to the transient response. Because the approach enables the estimation of probabilities for violating safety boundaries, it should be useful in a risk-based regulatory environment. It has the advantage of not requiring any substantial rewriting of existing safety analysis computer codes.
- 一般社団法人 日本原子力学会の論文
- 2011-04-01