[1] Smith K S. Assembly homogenization techniques for light water reactor analysis［J］.Progress in Nuclear Energy, 1986, 17(3): 303-335.

[2] 谢仲生. 压水堆核电厂堆芯燃料管理计算及优化［M］.北京: 原子能出版社, 2001.(Xie Zhongsheng. Fuel management computation and optimization of pressurized water reactors. Beijing: Atomic Energy Press, 2001)

[3] 柴晓明, 马永强, 王育威, 等. 堆芯中子学程序系统SARCS-4.0的开发及初步验证［J］.核动力工程, 2013(s1): 24-26.(Chai Xiaoming, Ma Yongqiang, Wang Yuwei, et al. Development and V&V of advanced neutronics code system SARCS-4.0. Nuclear Power Engineering, 2013(s1): 24-26)

[4] Lawrence R D. Progress in nodal methods for the solution of the neutron diffusion and transport equations［J］.Progress in Nuclear Energy, 1986, 17(3): 271-301.

[5] 田刚, 卢风顺. MPI／OPENMP＋CUDA高性能计算环境的配置及应用［J］.硅谷, 2011(17): 118-119.(Tian Gang, Lu Fengshun. Configuration and application of high performance computers based on MPI／OPENMP＋CUDA. Silicon Valley, 2011(17): 118-119)

[6] 张武生, 薛巍, 李建江. MPI并行程序设计实例教程［M］.北京: 清华大学出版社, 2009.(Zhang Wusheng, Xue Wei, Li Jianjiang. Parallel programming based on MPI. Beijing: Tsinghua University Press, 2009)

[7] Balay S, Brown J, Buschelman K, et al. PETSc users manual［R］.ANL-95/11 Rev 3.7, Argonne National Laboratory, 2013.

[8] Saad Y. Iterative methods for sparse linear systems［M］.Boston: PWS Publishing Company, 1996.

[9] Center A C. Benchmark Problem Book_IAEA, ANL-7416［R］.Computational Benchmark Problems Committee of the Mathematics and Computation Division of the American Nuclear Society, 1977.

[10] Modak R S, Jain V K. Sub-space iteration scheme for the evaluation of lambda-modes of finite-differenced multi-group neutron diffusion equations［J］.Annals of Nuclear Energy, 1996, 23(3): 229-237.

[11] Bandini. B R. A three-dimensional transient neutronics routine for the TRAC-PF1 reactor thermal hydraulic computer code［D］.Philadelphia: Pennsylvania State University, 1990.