基于改进多区delta-tracking方法的蒙特卡罗中子输运跟踪与临界计算验证

Study on Neutron Transport Tracking Using Improved Multi-regional delta-tracking Method in Monte Carlo Criticality Calculation

  • 摘要: 传统蒙特卡罗程序进行中子输运跟踪时,当中子穿越不同材料边界时需频繁大量地计算中子到材料边界的距离,若中子平均自由程大于局部模型的宏观尺寸,则大量的距离计算会显著降低中子输运跟踪效率。为弥补传统中子输运跟踪方法带来的潜在效率降低的缺陷,本文提出了改进多区delta-tracking中子输运跟踪方法,通过引入虚截面来对模型进行多区的虚拟均匀化处理,进而在中子输运跟踪时可不考虑材料边界穿越问题,理论上可提高中子输运跟踪效率。将改进多区delta-tracking中子输运跟踪方法在多功能辐射输运模拟仿真平台MOSRT系统中进行了程序实现。利用基准题和全堆芯模型开展了临界计算验证,证明了本文方法及程序的正确性和有效性。

     

    Abstract: In traditional Monte Carlo code relative to the neutron transport tracking process, the distances relative to the material boundaries must be computed frequently to determine the neutron transport length. However, if the neutron’s mean free path length is greater than the macro size of model, a huge amount of distances need to be computed. As a result, the computational efficiency of the neutron transport tracking will be degraded. The improved multi-regional delta-tracking method was introduced to solve the problem, in which the concept of the virtual cross-section was used to virtually homogenize multi-region in the model. Consequently, the efficiency of the neutron transport tracking could be improved theoretically without the distance calculations. The improved multi-regional delta-tracking method was incorporated into the MOSRT system, which was a multi-objective modeling and simulation platform for radiation transport system. Finally, the method was validated using the criticality benchmarks and its accuracy and efficiency are demonstrated.

     

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