摘要
数值反应堆是基于先进耦合建模技术、大规模并行计算技术、先进的验证与确认(V&V)等技术,建立在超级计算机上,可实现实际反应堆各种物理过程高精细模拟预测的复杂软件系统。它是实际反应堆“外在”和“内在”的镜像,是先进的核反应堆设计优化、高效运行、事故预测和应急以及新材料研发等的试验验证平台。本文在简略综述国内外典型数值反应堆研究成果的基础上,描述了本课题组近期开发的数值反应堆核心软件组成体系,分析了数值反应堆对计算资源和存储资源的需求,并介绍了目前正在开展的中国数值反应堆原型系统(CVR1.0)的研究进展。进展主要包括:两相子通道热工水力模拟软件、单相CFD热工水力模拟软件、多尺度材料辐照损伤模拟软件、直接3D中子输运特征线法模拟软件,以及这些软件与欧美CASL、NEAMS、RPV等相关软件的对比和在神威、曙光等超级计算机上的测试结果。
The virtual nuclear reactor is a sophisticated software system deployed on supercomputers to simulate physics processes or predict component behaviors inside real reactors.It heavily relies on advanced modeling and coupling methods,high performance computing and advanced verification and validation (V&V) techniques.It is supposed to provide an experimental verification platform for the design optimization of advanced nuclear reactors,efficient operation,accident prediction,emergency planning,and the development of new materials.In a word,the system is an “external” and “internal” mirror image of real reactors.Based on a brief overview of the research results of typical virtual nuclear reactors at home and abroad,the core software component of virtual nuclear reactor was explained,the high requirements for computing speed and storage were analyzed,and the recent achievements of the prototype of China Virtual Reactor (CVR1.0) were presented in this paper.The recent achievements of CVR1.0 contain some of its simulation tools including the two-phase sub-channel thermal- hydraulic simulation software,the single-phase CFD thermal-hydraulic simulation software,the multi-scale materials irradiation damage simulation software,and the method of characteristics software for direct 3D neutron transport simulation.Comparisons among these tools and their counterparts from CASL,NEAMS,and RPV in the U.S.A or Europe are made and listed concisely,as well as the results of performance analyses on supercomputers such as Sunway and Sugon series.
作者
杨文
胡长军
刘天才
汪岸
吴明宇
YANG Wen;HU Changjun;LIU Tiancai;WANG An;WU Mingyu(Division of Reactor Engineering Technology Research,China Institute of Atomic Energy,Beijing 102413,China;University of Science and Technology Beijing,Beijing 100083,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2019年第10期1821-1832,共12页
Atomic Energy Science and Technology
基金
国家重点研发计划重点专项资助项目(2017YFB0202301,2017YFB0202300)
关键词
数值反应堆
多物理耦合
中子物理
热工水力
材料计算
virtual nuclear reactor
multi-physics coupling
neutronics
thermal-hydraulics
materials calculation
