非能动压水堆核电厂乏燃料池风险评价

以非能动压水堆核电厂为研究对象，对可能引起乏燃料损伤的内部事件进行了风险评价。采用PSA软件RiskSpectrum建立事件树和故障树模型，进行乏燃料损伤频率（FDF）定量化。结果表明：在所有工况下总的FDF为2.05×10^-9/(堆•年)，远小于堆芯的损伤频率（约2.41×10^-7/(堆•年)）；即使在放射性完全释放的假设下，乏燃料损伤导致的大量放射性释放频率仍较堆芯损伤导致的大量放射性释放频率（约2.38×10^-8/(堆•年)）低1个量级；由于非能动压水堆核电厂有多重预防缓解措施以应对乏燃料池（SFP）事故，SFP风险远低于堆芯风险，可实现核安全导则的安全目标。

Spent Fuel Pool Risk Assessment for Passive PWR Nuclear Power Plant

For passive pressurized water reactor (PWR)nuclear power plant,spent fuel damage risk potentially induced by internal events was assessed.Spent fuel damage frequency (FDF)was quantified by event tree and fault tree model using probabilistic safety assessment software RiskSpectrum.For different operation conditions total FDF is 2.05×10 -9 per reactor-year which is much lower than core damage frequency (about 2.41 ×10 -7 per reactor-year).By assumption of completely radioactivity releasing,large radioactive release frequency caused by spent fuel damage is still one order of magnitude lower than that caused by core damage (about 2.38×10 -8 per reactor-year).Since the multiple prevention and mitigation measures in passive PWR nuclear power plant responding to spent fuel pool (SFP)accidents,the risk of SFP is much lower than that of reactor core,and the safety goals of nuclear safety guide can be achieved.