压水堆堆芯核设计软件包TORCH V2.0的验证与确认  

Validation and Verification for Nuclear Design Software Package TORCH V2.0 of Pressurized Water Reactor

作　　者：张斌[1] 李庆[1] 蔡云[1] 刘琨[1] 秦雪 王诗倩[1] 吉文浩 郭锐 赵晨 彭星杰 ZHANG Bin;LI Qing;CAI Yun;LIU Kun;QIN Xue;WANG Shiqian;JI Wenhao;GUO Rui;ZHAO Chen;PENG Xingjie(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213

出　　处：《原子能科学技术》2022年第11期2415-2421,共7页Atomic Energy Science and Technology

摘　　要：TORCH V2.0是由中国核动力研究设计院自主研发的压水堆堆芯核设计软件包,该软件包基于确定论两步法计算策略进行堆芯中子学计算,即组件均匀化计算和堆芯少群计算的模式。本文采用包括大亚湾、岭澳、方家山、秦山、海南昌江、福清等核电厂部分循环启动物理试验数据及核电厂运行数据对TORCH V2.0软件包进行验证与确认研究,对比的主要参数包括启动物理试验中的临界硼浓度、控制棒积分价值、硼微分价值及等温温度系数和核电厂运行过程中的临界硼浓度、组件径向功率、热点因子及焓升因子。数值结果表明:针对主流的方形栅格压水堆核电厂,TORCH V2.0软件包具有可靠的压水堆堆芯计算能力;对于启动物理试验和电厂运行过程中的主要参数,TORCH V2.0软件包具有较高计算精度,符合堆芯核设计验收准则。A conventional two-step approach of a transport calculation and a nodal diffusion calculation,such as CASMO/SIMULATE,APOLLO/SMART,was used in the light water reactor core design for decades.A new PWR core nuclear design software package named TORCH V2.0 was developed by Nuclear Power Institute of China(NPIC),and many advanced methodologies were implemented in TORCH V2.0 to enhance accuracy and performance.Based on the two-step calculation scheme,TORCH V2.0 mainly contains lattice physics code for assembly homogenization,link calculation code for few-group constant parameterization and core simulation code for few-group core calculation.The one-step direct heterogeneous calculation code KYLIN V2.0 based on fine-group structure was employed.KYLIN V2.0 was used to generate the homogenized parameters,including homogenized cross-section,diffusion coefficients,discontinuity factors and so on.Considering the fact that a certain state required by the reactor core calculation may be different from the ones provided by KYLIN V2.0,a process was required to provide a table between those neutronics few-group constants and state parameters based on the discrete points provided by lattice calculations.The code named PACFAC was used to provide the table for the core simulation code CORCA-3D.The neutron diffusion equation would be calculated for core fuel management in CORCA-3D.The calculation modules of each code were already verified against various benchmark problems,whereas the work presented in this paper focuses on the verification and validation(V&V)of linked code system TORCH V2.0 for the core design of pressurized water reactors(PWRs).The measured values of reactor startup physics test and nuclear power plant operation from six PWR NPPs(Daya Bay NPP,Ling’ao NPP,Fangjiashan NPP,Qinshan NPP,Hainan Changjiang NPP,Fuqing NPP)were utilized to do the comparison and analysis for V&V.Part of the reactor startup physics tests and a total of 85 cycles of 14 NPP units were simulated by TORCH V2.0.However,the content of the reacto

关 键 词：堆芯核设计 启动物理试验 核电厂运行数据 验证与确认 

分 类 号：TL329.2[核科学技术—核技术及应用]