临界-燃耗耦合计算方法

基于蒙特卡罗模拟方法，采用MCNP的多群计算程序模拟中子输运方程，并与栅元均匀化程序WIMS耦合，实现了临界-燃耗耦合计算。具体过程是:首先扩展MCNP的多群功能，将其能群扩展为69群；然后，由接口程序将WIMS程序产生69群共振、自屏宏观中子截面转化为ACE格式的多群截面；其次，将新产生的多群截面提供给MCNP，完成临界-燃耗计算；最后，利用此耦合程序进行了基准题校核计算以及实验对比。计算结果表明，此耦合程序是可靠和正确的。

Coupled calculation method of criticality and burnup

Based on Monte Carlo simulation method, we apply the multigroup calculation code of the MCNP to simulate theneutron transport equation. A coupled code of the MCNP code and the lattice homogeneous code WIMS is proposed to realize the coupled calculation of criticality and burnup. The specific process is as follows: firstly, the energy group is extended to 69-group owing to the extension of the multigroup calculation character of the MCNP code; secondly, we utilize the interface program to generate 69-group resonance and to transform the self-shield macroscopic neutron cross-section produced by the WIMS code into the multigroup cross-section of ACE format; thirdly, the new cross-section is supplied to the MCNP to finish criticality and burnup calculation; lastly, we use the coupled code to simulate benchmarks and the opposite experiment. The results indicate that the coupled code is correct and rational.Key words: