基于TRACE程序的大破口BEPU分析方法在独立审核计算中的应用

发布时间：2018-07-01 21:25

  本文选题：LBLOCA + 最佳估算及不确定性分析　； 参考：《原子能科学技术》2017年07期

【摘要】：我国某大功率非能动压水堆首次采用标准设计的方法。本文基于TRACE程序,采用最佳估算及不确定性分析方法对该电厂大破口失水事故开展了独立审核计算,并探讨了该方法在核安全审评中的应用。最佳估算结果表明,该压水堆大破口失水事故下包壳峰值温度低于验收准则限值。该计算结果可作为独立审核计算的重要部分应用于核电厂安全审评中。
[Abstract]:The standard design method is used for the first time in a high power passive pressurized water reactor (PWR) in China. In this paper, based on trace program, the method of optimal estimation and uncertainty analysis is used to carry out the independent audit and calculation of the water loss accident in the large break of the power plant, and the application of this method in the nuclear safety evaluation is discussed. The results show that the peak temperature of the cladding is lower than the limit of acceptance criterion. The calculated results can be used as an important part of the independent audit calculation in the safety evaluation of nuclear power plants.
【作者单位】： 环境保护部核与辐射安全中心;
【基金】：国家科技重大专项资助项目(2013ZX06002001-006,2015ZX06004001001-002)
【分类号】：TL364
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本文编号：2089199