[1] 张磊,贾铭椿,龚军军,等.反应堆辐射屏蔽计算方法与程序概述[J].核电子学与探测技术,2018,38(04):516-520. ZHANG Lei,JIA Mingchun, GONG Junjun, et al. Overview of calculation methods and codes for reactor radiation shielding[J]. Nuclear Electronics & Detection Technology, 2018,38(04):516-520. [2] Lee D. Hybrid deterministic-monte carlo methods for neutron particle transport[C]// Korean Nuclear Society Spring Meeting. 2012. [3] 庄思璇. 三维蒙特卡罗—离散纵标能量耦合中子输运计算方法研究[D].中国科学技术大学,2019. [4] 丁大钊,叶春堂,赵志祥,等.中子物理学-原理、方法与应用[M].北京:原子能出版社,2001. [5] Briesmeister J F. MCNP-A general monte carlo n particle transport code, version 4C[R]. Report LA-13709-M.Los Alamos National Laboratory, April 2000. [6] 谢仲生,主编.核反应堆物理分析[M].西安:西安交通大学出版社,2004. [7] Zheng Q, Shen W, Li Y Z, et al. A deterministic-stochastic energy-hybrid method for neutron-transport calculation[J]. Annals of Nuclear Energy, 2019,128: 292-299. [8] 韩静茹. 三维蒙特卡罗-离散纵标双向耦合屏蔽计算方法研究[D].华北电力大学,2012. [9] Zhao J, Li X, Wu B, et al. An automatic adaptive mesh generation method for weight window in Monte Carlo particle transport[J]. Annals of Nuclear Energy,2016,91:105-110. [10] 杨德锋,程和平.MCNP程序分段-衔接计算方法研究[J].核动力工程,2010,31(S2):48-53. YANG Defeng, CHENG Heping. Research on MCNP bootstrapping calculation method[J]. Nuclear Power Engineering, 2010,31(S2):48-53. [11] 黄倩倩,唐邵华,杨寿海.MC-MC耦合计算方法在核电厂中子屏蔽设计中的应用[J].辐射防护,2019,39(04):309-313. HUANG Qianqian, TANG Shaohua, YANG Shouhai. Application of MC-MC coupled method in neutron shielding analysis of NPP[J]. Radiation Protection, 2019,39(04):309-313. [12] Wijk A J van, Hoogenboom J E. A priori efficiency calculations for monte carlo applications in neutron transport[J]. Progress in Unclear Science and Technology,2011,2:722-732.DOI:10.15667/pnst.2.722. [13] Qiu Y S, Aufiero M, Wang K, et al. Development of sensitivity analysis capabilities of generalized responses to nuclear data in Monte Carlo code RMC[J]. Annals of Nuclear Energy, 2016, 97:142-152. |