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首页> 外文期刊>Annals of nuclear energy >Calculation of neutron importance function in fissionable assemblies using Monte Carlo method
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Calculation of neutron importance function in fissionable assemblies using Monte Carlo method

机译：蒙特卡罗方法计算裂变组件中子的重要度函数

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摘要

The purpose of the present work is to develop an efficient solution method for the calculation of neutron importance function in fissionable assemblies for all criticality conditions, based on Monte Carlo calculations. The neutron importance function has an important role in perturbation theory and reactor dynamic calculations. Usually this function can be determined by calculating the adjoint flux while solving the adjoint weighted transport equation based on deterministic methods. However, in complex geometries these calculations are very complicated. In this article, considering the capabilities of MCNP code in solving problems with complex geometries and its closeness to physical concepts, a comprehensive method based on the physical concept of neutron importance has been introduced for calculating the neutron importance function in sub-critical, critical and super-critical conditions. Tor this propose a computer program has been developed. The results of the method have been benchmarked with ANISN code calculations in 1 and 2 group modes for simple geometries. The correctness of these results has been confirmed for all three criticality conditions. Finally, the efficiency of the method for complex geometries has been shown by the calculation of neutron importance in Miniature Neutron Source Reactor (MNSR) research reactor.
机译：本工作的目的是基于蒙特卡洛计算方法，开发一种有效的求解方法，用于计算所有临界条件下可裂变组件中的中子重要性函数。中子重要性函数在微扰理论和反应堆动力学计算中具有重要作用。通常，该函数可以通过在确定性方法求解伴随加权输运方程的同时计算伴随通量来确定。但是，在复杂的几何形状中，这些计算非常复杂。在本文中，考虑到MCNP代码在解决复杂几何问题及其与物理概念的接近性方面的能力，引入了一种基于中子重要性物理概念的综合方法来计算亚临界，临界和中子的中子重要性函数。超临界条件。为此，提出了一种计算机程序。该方法的结果已通过ANISN代码计算以1和2组模式进行了基准测试，以简化几何。对于所有三个临界条件，这些结果的正确性都得到了确认。最后，通过计算微型中子源反应堆（MNSR）研究堆中子的重要性，证明了该方法对于复杂几何形状的效率。

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