池式钠冷快堆放射性释放风险概率安全评价事件树分析

Probabilistic Safety Assessment Event Tree Analysis of Radioactive Release Risk for Pool Type Sodium-cooled Fast Reactor

  • 摘要: 池式钠冷快堆的安全特性和放射性释放机制与压水堆有着显著不同,在核安全新要求下,亟待开展放射性释放风险概率安全评价(PSA)研究。本文以池式钠冷快堆为研究对象,通过分析放射性来源、包容边界及破坏包容边界完整性的严重事故现象,确定了池式钠冷快堆大量放射性释放的主要位置和释放模式,构建分析了放射性释放事件树。本文分析结果可为进一步开展池式钠冷快堆放射性释放风险PSA提供参考。

     

    Abstract: The safety characteristics and radioactive release mechanism of pool type sodium-cooled fast reactor (SFR) are significantly different from those of pressurized water reactor. Under the new nuclear safety requirements, the research on probabilistic safety assessment (PSA) of radioactive release risk for SFR is urgently needed. Taking the pool type SFR as the research object, the main position and mode of large radioactive release were identified and the radioactive release event trees were constructed by analyzing the radioactive source, the containment boundary and the severe accident that might challenge the integrity of the containment boundary. The results can serve as reference for further research on PSA of radioactive release risk for pool type SFR.

     

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