船用核动力装置小破口失水事故放射性后果分析

Radioactive consequence analysis of small-break LOCA for marine nuclear power plants

建立了小破口失水事故下热工水力分析与放射性源项计算耦合模型,利用研发的反应堆源项放射性计算软件(Nuclear source radioactive compute,NSRC),分别就不同破口尺寸的堆舱放射性泄漏进行了分析和研究,进一步研究了小破口失水事故,冷端安注和热端安注对堆舱放射性影响。结果表明:破口尺寸大小、安全注射位置及破口隔离时间直接影响堆舱放射性泄漏大小。本工作的分析结果为小型船用堆在小破口设计基准事故下,放射性污染后果分析及事故处置提供了依据。

The model of thermodynamic analysis coupling with radioactive resource compute in condition of small-break LOCA was established. The radioactive result of the reactor cabin for different break size was analyzed and investigated using developed software of Source Radioactive Compute for Nuclear Reactor （NSRC）. The radio- active effect had been evaluated in both conditions of cold leg and hot leg safety injections. The results show that the break inch, safety injection position and the isolation time of break can influence the radioactivity of reactor cabin directly, which may give some suggestion for the inspection of radioactivity and treatment of the design basis accident with different size small-break LOCA.