模块化2D/1D耦合特征线法MMOC程序开发及验证
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摘要
本文基于耦合求解的思想,轴向、径向均采用特征线法(MOC),通过开展2D/1D耦合MOC理论模型、模块化几何预处理方法研究,开发了2D/1D耦合MOC 3D中子输运求解程序MMOC,并开展了1D/2D/3DC5G7基准题验证。k_(eff)的相对误差分别为0.082%、0.045%、0.032%,该程序准确有效,计算精度满足中子输运计算的要求。
Based on the idea of coupling solution,the method of characteristic line(MOC)is applied in both axial and radial directions.By carrying out the 2D/1 Dcoupling MOC theory and modular geometry preprocessing method,a 2D/1 Dcoupling neutron transportation code MMOC was developed,and the 1D/2D/3D C5G7 benchmark was verified.The relative errors of k_(eff) are 0.082%,0.045%,and 0.032%.The MMOC code is reliable and can satisfy the computational requirement of neutron transportation.
Based on the idea of coupling solution,the method of characteristic line(MOC)is applied in both axial and radial directions.By carrying out the 2D/1 Dcoupling MOC theory and modular geometry preprocessing method,a 2D/1 Dcoupling neutron transportation code MMOC was developed,and the 1D/2D/3D C5G7 benchmark was verified.The relative errors of k_(eff) are 0.082%,0.045%,and 0.032%.The MMOC code is reliable and can satisfy the computational requirement of neutron transportation.
引文
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[2]刘紫静,谢金森,何丽华,等.全堆芯中子输运计算方法研究现状[J].科技资讯,2015,13(21):1-4.LIU Zijing,XIE Jinsen,HE Lihua,et al.Research status of neutron transport calculation method for full core[J].Scientific and Technological Information,2015,13(21):1-4(in Chinese).
[3]KNEZEVIC J,HERNANDEZ H,FOGAL T,et al.Visual simulation steering for a 3D neutron transport AGENT code system[C]∥Proceedings of the 1st International Nuclear and Renewable Energy Conference.Amman:[s.n.],2010.
[4]柴晓明,姚栋,王侃.基于特征线方法的三维中子输运程序(Ⅰ)——边界条件的插值处理[J].核动力工程,2010,31(2):11-15.CHAI Xiaoming,YAO Dong,WANG Kan.Three dimension neutron transport characteristics method code(Ⅰ)—Interpolation treatment of boundary condition[J].Nuclear Power Engineering,2010,31(2):11-15(in Chinese).
[5]吴文斌.基于并行技术的2D/1D耦合三维全堆输运方法研究[D].北京:清华大学,2014.
[6]JOO H G,CHO J Y,KIM K S,et al.Methods and performance of a three-dimensional wholecore transport code DeCART[C]∥Proceedings of PHYSOR 2004Conference.Chicago:American Nuclear Society,2004.
[7]汤春桃.中子输运方程特征线解法及嵌入式组件均匀化方法的研究[D].上海:上海交通大学,2009.
[8]KOSAKA S,SAJI E.Transport theory calculation for a heterogeneous multi-assembly problem by characteristics method with direct neutron path linking technique[J].Journal of Nuclear Science&Technology,2000,37(12):1 015-1 023.
[9]YAMAMOTO A,TABUCHI M,SUGIMURA N,et al.Derivation of optimum polar angle quadrature set for the method of characteristics based on approximation error for the Bickley function[J].Journal of Nuclear Science&Technology,2007,44(2):129-136.
[10]YAMAMOTO A,TABUCHI M,SUGIMURA N,et al.Non-equidistant ray tracing for the method of characteristics[C]∥Proceedings of Topical Meeting on Mathematics and Computation,Super computing,Reactor Physics and Nuclear and Biological Applications.Avignon:[s.n.],2005.
[11]LEONARD A,MCDANIEL C T.Optimal polar angles and weights for the characteristics method[J].Transactions of the American Nuclear Society,1995,73:172.
[12]LEWIS E E,SIMITH M A,TSOULFANIDIS N,et al.Benchmark specification for deterministic 2D/3D MOX fuel assembly transport calculations without spatial homogenization,C5G7MOX[R].NEA/NSC/DOC:OECD Nuclear Energy Agency,2001.
[13]XIAO S,YANG X,SATVAT N,et al.Modeling reactors with AGENT:Verification,validation,efficiency analysis and 3D[C]∥Proceedings of the 1st International Nuclear and Renewable Energy Conference.Amman:[s.n.],2010.