中国先进研究堆全堆芯扩散计算

Whole Core Diffusion Calculation for China Advanced Research Reactor

基于物理启动、同位素生产以及空间燃耗不同考虑的全堆芯模型,采用少群扩散方法对中国先进研究堆(CARR)堆芯进行计算。通过对选定的换料方案进行堆芯第1～3炉的临界计算,得到了各炉初/末期的反应性、中子注量率以及功率分布。并且采用隐式燃耗方法模拟了CARR堆芯燃耗过程,得到了堆芯燃耗分布,分析了堆运行过程中产生的裂变产物份额并给出了中毒反应性效应。确定了CARR的基本物理特性参数,完成了CARR物理详细设计工作,为CARR最终安全分析报告的编写以及将来的运行提供必要的数据。

The neutronics analysis of China Advanced Research Reactor is carried out with the diffusion method by using the whole core module in this paper.Based on the critical calculation of thecore of different periods,the reactivity and the neutron flux and power distribution from the 1^(st)cycle to the 3^(rd)cycle are given. The burnup calculation of CARR is done in the indirect way.In the calculation,the burnup distribution of CARR is given and the fraction of the fission productions is obtained.Meanwhile the reactivity of the fission poison is analyzed in this paper.