中子输运计算集成软件平台的研究与设计  

Study and Design of Integrated Software Platform for Neutron Transport Calculation

作　　者：李磊[1] 王世庆[1] 李伟 柳建[1] LI Lei;WANG Shi-qing;LI Wei;LIU Jian(Southwestern Institute of Physics,Chengdu,Sichuan Prov.610225,China;China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen,Guangdong Prov.518000,China)

机构地区：[1]核工业西南物理研究院,四川成都610225 [2]中广核研究院有限公司,广东深圳518000

出　　处：《中国核电》2022年第2期152-158,共7页China Nuclear Power

基　　金：国家重点研发计划(No.2020YFB1902000)支持。

摘　　要：为提高中子输运仿真的工程效率、降低前后处理复杂性,减少对工程人员经验的依赖,基于CAD软件的BREP输出格式、蒙卡程序MCNP的计算核心,开发了集成输入卡自动生成、输运计算自动调用、计算结果图形化处理功能的软件平台,实现了堆芯中子输运计算的一体化处理。通过对某堆型堆芯临界计算,结果表明该软件平台能较好用于反应堆堆芯设计方案的分析评估,工作效率高、经验因素依赖少,为后续进一步开发适用范围更广的通用软件平台建立了良好基础。In order to improve the engineering efficiency of neutron transport simulation,degrade the complexity of pre-and post-processing,and reduce the dependence on the experience of engineers,based on the BREP output format of CAD software and the calculation core of MCNP,a software platform is developed to integrate the functions of automatic generation of the input card,automatic call of transport calculation and graphical processing of calculation results.The results of core criticality calculation for a certain reactor type show that the software platform can be used for analysis and evaluation of the reactor core design scheme with high working efficiency and little dependence on experience factors,it has established a good foundation for further developing the universal software platform with wider application range.

关 键 词：BREP MCNP 中子输运 临界计算 结果后处理 

分 类 号：TM623[电气工程—电力系统及自动化]