快堆假想堆芯解体事故程序研发

Research and Development of Hypothetical Core Disruptive Accident Code in Fast Breeder Reactor

摘要: 钠冷快中子反应堆是以钠作为冷却剂的第4代核能系统之一，为保证快堆在严重事故下能够包容放射性物质，对快堆假想堆芯解体事故进行准确模拟计算是非常必要和迫切的。采用改进型B-T模型对快堆假想堆芯解体事故进行分析是目前国际上主要的分析方法，为能更好地分析快堆假想堆芯解体事故，在改进型B-T模型的基础上引入快堆实际的堆芯反应性系数分布函数。本工作与法国的EPIXCOPOS程序计算结果的对比验证表明，程序模型能对快堆假想堆芯解体事故进行保守分析。

Abstract: The liquid metal fast breeder reactor (FBR) is one of the generation Ⅳ nuclear powers, and it is necessary to analyze core disruptive accident of FBR so that the system can contain the radioactive material. The modified Bethe-Tait model is the general method of core disruptive accident analysis. In order to analyze the hypothetical core disruptive accident of FBR, based on the Bethe-Tait model, the core power distribution of FBR was added to the procedure. Compared with the French EPIXCOPOS code results, it is shown that the procedure can analyze core disruptive accident of FBR.