钠冷快堆先进建模与高性能粒子输运数值模拟进展  

Progress in Advanced Modeling and Numerical Simulation of High-performance Particle Transport for Sodium-cooled Fast Reactor

作　　者：周培德[1] 薛小刚[1] 吴明宇[1] 王事喜[1] 吴宗芸 霍兴凯 高鑫钊 张强[1] 付元光[2] 周生诚 刘晨[1] 马建明[1] ZHOU Peide;XUE Xiaogang;WU Mingyu;WANG Shixi;WU Zongyun;HUO Xingkai;GAO Xinzhao;ZHANG Qiang;FU Yuanguang;ZHOU Shengcheng;LIU Chen;MA Jianming(China Institute of Atomic Energy,Beijing 102413,China;Software Center for High Performance Numerical Simulation,China Academy of Engineering Physics,Beijing 100088,China)

机构地区：[1]中国原子能科学研究院,北京102413 [2]中国工程物理研究院高性能数值模拟软件中心,北京100088

出　　处：《原子能科学技术》2022年第11期2395-2407,共13页Atomic Energy Science and Technology

基　　金：中核集团青年科技创新团队项目(FC192012000220)。

摘　　要：钠冷快堆高性能数值模拟基于先进建模技术、大规模并行计算技术,实现大型池式快堆多物理过程精细化分析计算,包括池式结构快堆堆本体范围中子和γ射线深穿透计算,堆芯范围pin-by-pin精细化功率分布计算及输运-燃耗耦合计算,堆芯核-热子通道耦合计算。建立快堆高性能多物理耦合计算系统,并实现可视化输入和输出,可快速获得堆芯或堆本体范围更为清晰的物理图像,为反应堆设计迭代、整体方案优化等提供支撑。The fuel assembly and fuel rod bundle of sodium-cooled fast reactor are arranged in a triangle form.The fuel assembly adopts closed structure deign without mixing of coolant between assemblies,which is cooled by the sodium coolant through the distribution header on the bottom of the core to accomplish the matching of coolant and nuclear power and flattening the outlet temperature of the reactor core.It is of great significance for the core design and flow distribution scheme to carry out the whole core pin-by-pin refinement power distribution and neutronic-thermal coupling calculation.There are many internal components and complex structures in the pool type fast reactor container including the core,the internal shielding structure,the primary main pump,intermediate heat exchanger,independent heat exchanger and loading and unloading elevators which are arranged around the core.The design of neutron extraction channel in the direction of loading and unloading lifting devices leads to the asymmetry of the structure in the reactor container.It causes obvious anisotropic scattering in the process of neutron transport calculation,which is also a typical deep penetration problem,so more reliable and accurate calculation results require three-dimensional calculation with the whole range of the reactor container.The above problems pose challenges to modeling and neutron transport calculation.The high-performance simulation system of sodium-cooled fast reactor adopts advanced modeling technology,large-scale parallel computing technology,transport-burnup coupling function,core-assembly-lattice multi-level mapping and conversion technology to realize the full range three-dimensional fine modeling and multi-physical coupling calculation,including the shielding calculation of the container of pool structure fast reactor,the deep penetration calculation of neutron transport of detectors outside the reactor,pin-by-pin refined power distribution calculation,transport burnup coupling calculation and full core neutronic-thermal su

关 键 词：钠冷快堆 高性能数值模拟 先进建模 并行计算 耦合 

分 类 号：TL32[核科学技术—核技术及应用]