1 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, 3(21): 1-4. LIU Zijing, XIE Jinsen, HE Lihua, et al. The research status of whole core neutron transport calculation method[J]. Science & Technology Information, 2015, 3(21): 1-4.2 陈珍平, 王电喜, 何桃, 等. 基于CAD技术的特征线中子输运计算程序开发[J]. 核科学与工程, 2012, 32(4): 354-359. DOI: 10.3969/j.issn.0258-0918.2012.04.011. CHEN Zhenping, WANG Dianxi, HE Tao, et al. Development of a CAD-based neutron transport code with the method of characteristics[J]. Chinese Journal of Nuclear Science and Engineering, 2012, 32(4): 354-359. DOI: 10.3969/j.issn. 0258-0918.2012.04.011.3 Cho J Y, Joo H G, Kim K S. Cell based CMFD formulation for acceleration of whole-core method of characteristics calculation[J]. Nuclear Engineering and Technology, 2002, 34(3): 250-258.4 Jevremovic T, Vujic J, Tsuda T. ANEMONA: method of characteristics based on the R-function 2D solid modeler[C]. ANS/ENS International Winter Meeting and Embedded Topical Meetings, Washington DC, USA, 1998.5 Jevremovic T, Vujic J, Tsuda K. ANEMONA-a neutron transport code for general geometry reactor assemblies based on the method of characteristics and R-function solid modeler[J]. Annals of Nuclear Energy, 2001, 28(2): 125-152.6 Cho N Z. Fundamentals and recent developments of reactor physics methods[J]. Nuclear Engineering and Technology, 2005, 37(37): 25-78.7 Yamamoto A, Endo T, Tabuchi M, et al. AEGIS: an advanced lattice physics code for light water reactor analyses[J]. Nuclear Engineering and Technology, 2010, 42(5): 500-519.8 田超, 郑友琦, 李云召, 等. 基于组件模块化特征线方法的中子输运计算研究[J]. 核动力工程, 2015, 3: 157-161. TIAN Chao, ZHENG Youqi, LI Yunzhao, et al. Neutron transport study based on assembly modular ray tracing MOC method[J]. Nuclear Power Engineering, 2015, 3: 157-161.9 汤春桃, 张少泓. 以栅元为模块进行特征线跟踪的中子输运方程解法[J]. 核动力工程, 2009, 30(4): 32-36. TANG Chuntao, ZHANG Shaohong. Study on method of characteristics based on cell modular ray tracing[J]. Nuclear Power Engineering, 2009, 30(4): 32-36.10 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. TANG Chuntao. Investigation on method of characteristics for solving neutron transport equation and embedded assembly homogenization method[J]. Shanghai: Shanghai Jiao Tong University, 2009.11 叶志民, 张鹏, 刘峙嵘. 基于蒙特卡罗均匀化的堆物理分析方法[J]. 核技术, 2014, 37(6): 060603. DOI: 10.11889/j.0253-3219.2014.hjs.37.060603. YE Zhimin, ZHANG Peng, LIU Zhirong. Reactor physics analysis method based on Monte Carlo homogenization[J]. Nuclear Techniques, 2014, 37(6): 060603. DOI: 10.11889/j.0253-3219.2014.hjs.37.060603.12 Smith K S, Rhodes J D. CASMO-4 characteristics method for two-dimensional PWR and BWR core calculations[C]. ANS/ENS International Winter Meeting and Embedded Topical Meetings, Washington DC, USA, 2003.13 Zika M R, Adams M L. Transport synthetic acceleration for long-characteristics assembly-level transport problems[J]. Nuclear Science and Engineering, 2000, 134(2): 135-158.14 Shinya Kosaka, Etsuro Saji. Transport theory calculation for a heterogeneous multi-assembly problem by characteristics method with direct neutron path linking technique[J]. Journal of Nuclear Science and Technology, 2012, 37(12): 1015-1023.15 Yamamoto A, Tabuchi M, Sugimura N, et al. Non-equidistant ray tracing for the method of characteristics[C]. Topical Meeting on Mathematics and Computation, Super computing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Avignon, France, 2005.16 Leonard A, McDaniel C T. Optimal polar angles and weights for the characteristics method[J]. Transactions of the American Nuclear Society, 1995: 73.17 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 and Technology, 2007, 44(2): 129-136.18 Hong-chul Kim, Chi Young Han, Jong Kyung Kim. Twodant solutions for the 2-D C5G7 MOX benchmark[J]. Progress in Nuclear Energy, 2004, 45(2-4): 201-213. |