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美国橡树岭国家实验室开发的SCALE/TRITON程序广泛用于反应堆临界安全、中子物理、辐射屏蔽和灵敏度与不确定度等方面的计算分析。基于SCALE/TRITON程序,采用等效体积、均匀混合和平均截面等三种外部耦合方法,处理单流双区熔盐堆的燃耗计算,解决了SCALE/TRITON程序在计算中不能精确反映流动燃料周期性均匀混合的问题。研究表明平均截面法与均匀混合法的计算结果几乎完全一致,与橡树岭文献结果也能很好符合,等效体积法因为没有考虑堆芯分区结构的差异而导致计算结果与其他两种方法偏离较大。基于SCALE/TRITON发展的平均截面法,放宽了对步长的要求,具有准确性好、计算效率高的优点,适用于熔盐堆两区(或多区)的堆芯设计与燃耗性能分析,具有重要的应用意义。
The SCALE / TRITON program developed by Oak Ridge National Laboratory is widely used in computational analysis of reactor critical safety, neutron physics, radiation shielding, and sensitivity and uncertainty. Based on SCALE / TRITON program, three kinds of external coupling methods such as equivalent volume, uniform mixing and average section are adopted to deal with the fuel consumption calculation of single-flow dual-zone molten salt reactor, which solves the problem that SCALE / TRITON program can not accurately reflect the flowing fuel Periodic uniform mixing problems. The results show that the average cross-section method and the uniform mixing method are almost exactly the same, which are in good agreement with the results of Oak Ridge literature. The equivalent volume method deviates from the other two methods because it does not consider the difference of the core partition structure Larger. Based on the average cross section method developed by SCALE / TRITON, the requirements for step length are relaxed. The method has the advantages of good accuracy and high computational efficiency, and is applicable to the core design and fuel consumption performance analysis of two (or more) regions of the molten salt reactor , Has important application meaning.