| 1 吴治华, 赵国庆, 陆福全. 原子核物理实验方法[M]. 北京:原子能出版社, 1994:36-69. WU Zhihua, ZHAO Guoqing, LU Fuquan. Experimental method of nuclear physics[M]. Beijing:Atomic Energy Press, 1994:36-69.2 史永谦. 核反应堆中子学实验技术[M]. 北京:中国原子能出版社, 2011:332-334. SHI Yongqian. Nuclear reactor neutron experiment technology[M]. Beijing:China Atomic Energy Press, 2011:332-334.3 ASTM E263-13:Standard test method for measuring fast-neutron reaction rates by radioactivation of iron[S]. USA:ASTM, 2013.4 ASTM E264-08:Standard test method for measuring fast-neutron reaction rates by radioactivation of nickel[S]. USA:ASTM, 2008.5 ASTM E264-07:Standard test method for measuring reaction rates and fast-neutron fluences by radioactivation of sulfur-32[S]. USA:ASTM, 2007.6 蒋励, 胡俊, 文德智. 14 MeV中子注量率测量技术比对研究[J]. 中国核科技报告, 2005, (1):66-75. JIANG Li, HU Jun, WEN Dezhi. Study on measurement technique contrast of 14-MeV neutron fluence[J]. China Nuclear Science and Technology Report, 2005, (1):66-75.7 郑春, 吴建华, 李建胜, 等. 活化法测量CFBR-II堆中子注量和中子能谱[J]. 核动力工程, 2004, 25(1):93-96. ZHENG Chun, WU Jianhua, LI Jiansheng, et al. Neutron spectra and fluence of CFBR-II reactor measured by foils activation technique[J]. Nuclear Power Engineering, 2004, 25(1):93-96.8 李达, 张文首, 江新标, 等. 西安脉冲堆大空间中子辐照实验平台辐射场参数测量[J]. 原子能科学技术, 2014, 48(7):1243-1249. LI Da, ZHANG Wenshou, JIANG Xinbiao, et al. Parameter measurement for radiation field of large space neutron irradiation platform in Xi'an pulsed reactor[J]. Atomic Energy Science and Technology, 2014, 48(7):1243-1249.9 ASTM E720-11:Standard guide for selection and use of neutron sensors for determining neutron spectra employed in radiation-hardness testing of electronics[S]. USA:ASTM, 2011.10 Macfarlane R E. Code system for producing, pointwise and multigroup neutron and photon cross sections from ENDF/B data[R]. New Mexico:Los Alamos Nuclear Laboratory, 2000.11 李星月, 归寿造. ORIGEN-2程序的移植、扩充及其应用[J]. 计算物理, 1991, 3:325-329. LI Xingyue, GUI Shouzao. The transplantation, augmentation and application of ORIGEN-2 code[J]. Chinese Journal of Computational Physics, 1991, 3:325-329.12 XMC Team. MCNP:a general Monte Carlo n-particle transport code[R]. Version 5. New Mexico:Los Alamos Nuclear Laboratory, 2003. |
