MCNP-FISPACT耦合燃耗计算程序开发与测试

反应堆堆芯的燃耗计算关系到堆芯的燃料管理,并直接影响堆芯的经济性评估,因此如何快速且准确地对堆芯进行燃耗计算一直是反应堆物理设计的研究重点之一。随着反应堆的发展,其几何结构和物理特性日渐复杂,现有的一维、二维耦合燃耗程序因其在几何处理上的限制,难以满足先进反应堆精细设计分析的要求。为对复杂反应堆堆芯的燃耗情况进行计算,结合粒子输运程序MCNP 处理复杂几何和燃耗程序FISPACT处理核素全面的特点,开发了接口程序耦合MCNP 和FISPACT来进行燃耗计算,并对耦合程序进行了计算验证。采用了IAEA 基准校核例题和CFETR中国聚变工程实验堆例题进行程序验证,经计算得出的有效倍增因子随燃耗的变化曲线和TBR等数据与标准例题的结果符合良好,其误差在可接受范围内。

Testing and analysis of coupled program of MCNP and FISPACT

The burnup calculation of reactors is related to the fuel management of the reactor, and directly affect the economic evaluation of the core, therefore how to calculate burnup characteristics of reactors faster and better is an important part of the research. With the development of the reactor, its geometry becomes more and more complex. Some of the existing one-dimensional or two-dimensional burnup coupled program, due to restrictions on the geometry processing, are difficult to meet the requirements of advanced reactors design and analysis. In this paper, we combine the advantages of MCNP which is good at dealing with complex geometry, and FISPACT which could process radionuclides very comprehensively. The FISPACT and MCNP were coupled for burnup calculation, and the coupled program was verified by calculating the examplesIAEA ADS-benchmark and fusion reactor example. The calculation results of keff and tritium breeding ratio(TBR) by the coupled program are in good agreement with the standard results, and the errors are within acceptable ranges.