Coupled calculation method of criticality and burnup
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摘要: 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。Abstract: Based on Monte Carlo simulation method, we apply the multigroup calculation code of the MCNP to simulate the neutron 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.
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