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
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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。
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.
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.
引文
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[12] Organization for Economic Cooperation and Development (OECD). International handbook of evaluated criticality safety benchmarks[M]. France: Nuclear Energy Agency, 2006.
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[15] HORELIK N, HERMAN B, FORGET B, et al. Benchmark for evaluation and validation of reactor simulations (BEAVRS), v1.0.1[C]//International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley: [s. n.], 2013.
[2] MARTIN W R. Challenges and prospects for whole-core Monte Carlo analysis[J]. Nuclear Engineering and Technology, 2012, 44(2): 151-160.
[3] SIEGEL A R, SMITH K, ROMANO P K, et al. Multi-core performance studies of a Monte Carlo neutron transport code[J]. International Journal of High Performance Computing Applications, 2014, 28(1): 87-96.
[4] TRAMM J R, SIEGEL A R. Memory bottlenecks and memory contention in multi-core Monte Carlo transport codes[J]. Annals of Nuclear Energy, 2015, 82: 195-202.
[5] 许淑艳. 蒙特卡罗方法在实验核物理中的应用[M]. 北京:原子能出版社,2006:8.
[6] WOODCOCK E, MURPHY T, HEMMING P, et al. Techniques used in the GEM code for Monte Carlo neutronics calculation in reactor and other system of complex geometry[R]. USA: Argonne National Laboratory, 1965.
[7] LEPPANEN J. Performance of Woodcock delta-tracking in lattice physics applications using the serpent Monte Carlo reactor physics burnup calculation code[J]. Annals of Nuclear Energy, 2010, 37(5): 715-722.
[8] COWAN P, DOBSON G, WRIGHT G A, et al. Recent developments to the Monte Carlo code MCBEND[J]. Journals, 2009, 168(3): 780-784.
[9] 陈珍平,谢金森,郭倩,等. 多功能辐射输运模拟仿真平台开发与初步应用[J]. 南华大学学报:自然科学版,2018,32(5):12-18. CHEN Zhenping, XIE Jinsen, GUO Qian, et al. Development and application of the multi-objective modeling and simulation platform for radiation transport system[J]. Journal of University of South China: Science and Technology, 2018, 32(5): 12-18(in Chinese).
[10] 宋婧,孙光耀,陈珍平,等. 蒙特卡罗有效增殖因子计算方法研究[J]. 核科学与工程,2015,35(2):241-245. SONG Jing, SUN Guangyao, CHEN Zhenping, et al. Study on Monte Carlo k-effective calculation method[J]. Nuclear Science and Engineering, 2015, 35(2): 241-245(in Chinese).
[11] LEPPANEN J. Development of a new Monte Carlo reactor physics code[D]. Helsinki: VTT Technical Research Centre of Finland, Helsinki University of Technology, 2007.
[12] Organization for Economic Cooperation and Development (OECD). International handbook of evaluated criticality safety benchmarks[M]. France: Nuclear Energy Agency, 2006.
[13] KIM K T, SUH J M. Development of an advanced PWR fuel for OPR1000s in Korea[J]. Nuclear Engineering and Design, 2008, 238(10): 606-613.
[14] HOOGENBOOM J E, MARTIN W R, PETROVIC B. The Monte Carlo performance benchmark test: Aims, specifications and first results[C]//International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Brazil: [s. n.], 2011.
[15] HORELIK N, HERMAN B, FORGET B, et al. Benchmark for evaluation and validation of reactor simulations (BEAVRS), v1.0.1[C]//International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley: [s. n.], 2013.