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蒙特卡罗程序LoongSTARS MCX在快堆屏蔽问题中的计算
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Abstract:
快中子反应堆是我国核电发展三步走战略的关键一环，对于快堆屏蔽问题的计算是快堆设计与发展的重要工作，采用我国自主研发的液态金属冷却快堆设计分析龙码系统中的蒙特卡罗–确定论耦合粒子输运计算软件LoongSTARS MCX，通过模拟选定的SINBAD基准实验，验证LoongSTARS MCX程序在快堆屏蔽问题上的计算能力。整个验证以两种方式进行，首先通过与MCNP程序的计算结果对比，验证LoongSTARS MCX程序的功能性和计算精度。其次，将计算结果与SINBAD实验结果进行对比，验证LoongSTARS MCX程序的有效性和计算准度。结果表明，LoongSTARS MCX程序结果与MCNP程序结果高度吻合，相对偏差在±20%以内，并且与实验值符合较好，偏差在合理可靠范围内，LoongSTARS MCX程序可以用于快堆屏蔽问题上应用研究，具有良好的计算准度与精度。
Fast neutron reactor is a key link in the three-step strategy of nuclear power development in our country, and the calculation of shielding problem of fast reactor is an important work for the design and development of a fast reactor, using the Monte Carto-deterministic method coupled particle transport calculation software LoongSTARS MCX in the LONGCODE system for liquid metal cooled fast reactor design analysis developed by our country, we simulated the selected SINBND benchmark experiment, verify the computing power of LoongSTARS MCX program on fast reactor shielding problem. The whole validation was carried out in two ways. First, the functionality and accuracy of the LoongSTARS MCX program were verified by comparing the results with those of the MCNP program. Secondly, compared with the Sinbad experimental results, the validity and accuracy of the LoongSTARS MCX program are verified. The results show that the results of LoongSTARS MCX are in good agreement with those of MCNP, the relative deviation is less than ±20%, and the deviation is in a reasonable and reliable range, the LoongSTARS MCX program can be used to study the shielding problem of fast reactor with good calculation accuracy and precision.
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