直接三维中子输运特征线法并行计算软件的实现  

Parallel Implementation of Direct 3D Neutron Transport Method of Characteristics

作　　者：汪岸 胡长军[1] 王根 曹敏[1] 单浩栋 胡赟[2] 杨文[2] 刘天才[2] WANG An;HU Changjun;WANG Gen;CAO Min;SHAN Haodong;HU Yun;YANG Wen;LIU Tiancai(University of Science and Technology Beijing,Beijing 100083,China;China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]北京科技大学,北京100083 [2]中国原子能科学研究院,北京102413

出　　处：《原子能科学技术》2021年第9期1559-1568,共10页Atomic Energy Science and Technology

基　　金：国家重点研发计划重点专项(2017YFB0202303,2017YFB0202300)。

摘　　要：作为中子输运问题的一种重要确定论方法,特征线法(MOC)具有强几何适应性、计算流程简洁、易于大规模并行的优点。ANT-MOC是自主开发的中国数值反应堆1.0(CVR1.0)中的三维特征线法中子输运计算程序,主要用于压水堆、快堆的堆芯输运计算。ANT-MOC支持基于构造实体几何(CSG)的复杂几何建模、高效的用户输入方式、面向矩形/六边形网格的射线追踪算法,以及基于轨迹链分解的并行算法和负载平衡策略。在国产超算上,ANT-MOC可以扩展到约10万处理器核,并行效率在50%以上。针对压水堆、快堆计算问题进行验证和参数敏感性分析,结果表明ANT-MOC计算结果具有较好的稳定性和准确度。As an important deterministic method for the neutron transport problem,the method of characteristics(MOC)has many advantages of strong geometric adaptability,simple calculation diagram,and easy large-scale parallel.ANT-MOC is a self-developed three-dimensional MOC neutron transport code in the China Virtual Reactor 1.0(CVR1.0),which is mainly used for steady state core transport calculations of pressurized water reactor(PWR)and fast breeder reactor(FBR).ANT-MOC supports complex geometric modeling based on constructed solid geometry(CSG),efficient user input methods,ray tracing algorithms for rectangular/hexagonal grids and parallel algorithms and load balance based on trajectory chain decomposition.On domestic supercomputers in China,ANT-MOC can scale to about 100000 processor cores to reach a parallel efficiency above 50%.The verification and parameter sensitivity analysis were conducted with PWR and FBR core calculation problems.The results show that the calculation results of ANT-MOC can achieve good stability and accuracy.

关 键 词：中子输运 特征线法 并行计算 负载平衡 数值反应堆 快堆 

分 类 号：TL329[核科学技术—核技术及应用]