基于数字化反应堆物理计算程序SHARK的一步法输运计算方法研究  

Research on Direct Transport Calculation Method Based on Numerical Nuclear Reactor Physics Code SHARK

作　　者：赵晨 赵文博[1] 张宏博 王博 陈长[1] 彭星杰 宫兆虎[1] 曾未[1] 李庆[1] Zhao Chen;Zhao Wenbo;Zhang Hongbo;Wang Bo;Chen Zhang;Peng Xingjie;Gong Zhaohu;Zeng Wei;Li Qing(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,成都610213

出　　处：《核动力工程》2023年第4期33-40,共8页Nuclear Power Engineering

基　　金：国家自然科学基金项目(12005214)。

摘　　要：为建立基于数字化反应堆技术的新一代反应堆物理计算方法,实现数字化反应堆高保真建模、高分辨率高精度计算,基于数字化反应堆物理计算程序SHARK,开展了一步法输运计算方法研究,建立并比较了二维/一维方法及准三维特征线输运方法;基于空间区域分解及粗网有限差分(CMFD)的大规模并行加速技术,实现了棒状堆芯及板状堆芯的全堆规模一步法输运计算。数值结果与蒙特卡罗程序基准解相比,特征值偏差小于100pcm(1pcm=10^(-5)),最大棒功率、板功率偏差小于3%,验证了SHARK程序一步法输运计算方法具有良好计算精度,能够适用于棒状、板状堆芯等多应用场景。In order to establish the next-generation reactor physics calculation method based on the numerical nuclear reactor technology and realize high-fidelity modeling,high-resolution and high-precision calculation,the research of direct transport method was conducted based on the numerical nuclear reactor physics code SHARK,and 2D/1D and quasi-3D MOC methods were built and compared.Based on the large-scale parallel acceleration technology of domain decomposition and coarse mesh finite difference(CMFD),the whole reactor direct transport calculation was realized for the pin-type and plate-type cores.Compared with Monte-Carlo reference results,eigenvalue differences were less than 100pcm(1pcm=10^(-5))and maximum pin/plate powers were less than 3%.Numerical results showed the good accuracy of SHARK in the direct transport calculation,and can be apllied in multi-application scenarios of pin-type and plate-type cores.

关 键 词：数字化反应堆 二维/一维方法 准三维特征线方法 SHARK 

分 类 号：TL329[核科学技术—核技术及应用]