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^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n,p)^(56,54)Mn反应截面计算及普适性模型参数优化研究
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作者 霍东英 刘昌奇 +6 位作者 韩超 吴康 胡志杰 户志鸣 于筱雪 姚泽恩 韦峥 《原子核物理评论》 CAS CSCD 北大核心 2021年第2期221-228,共8页
基于中子与Fe发生反应产生“氢泡”,及“氦泡”对新型核能利用系统壁材料的影响,开展了中子诱发^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n,p)^(56,54)Mn反应截面计算研究工作。本工作根据现有的^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n... 基于中子与Fe发生反应产生“氢泡”,及“氦泡”对新型核能利用系统壁材料的影响,开展了中子诱发^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n,p)^(56,54)Mn反应截面计算研究工作。本工作根据现有的^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n,p)^(56,54)Mn反应实验数据、评价数据,对TALYS程序调用的物理模型(包括能级密度、对修正、核温度、光学势参数等)进行参数调校,得到了一组普适性强的模型参数。基于调校的参数,本工作采用核反应程序TALYS理论计算^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n,p)^(56,54)Mn反应的截面、能量微分截面以及双微分截面,全部数据都能与实验数据、评价数据符合较好,且适用于较宽的中子能量区间0~175 MeV。本工作提出了^(56,54)Fe(n,α)^(53,51)Cr,^(56,54)Fe(n,p)^(56,54)Mn反应的普适性模型参数,促进了核反应理论的发展,为核数据的评价奠定了基础。 展开更多
关键词 ^(56 54)Fe(n α)^(53 51)Cr ^(56 54)Fe(n p)^(56 54)Mn 反应截面 微分截面 双微分截面
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^(235)U enrichment detection system for nuclear fuel rod based on compact D–D neutron generator 被引量:3
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作者 WU Kang LIU XingYu +11 位作者 YANG Xu LIU ChangQi huo dongying BAI XiaoHou HAN Chao JIANG QiaoYue ZHANG Hang PENG JinQiu ZHANG Yu WANG JunRun YAO ZeEn WEI Zheng 《Science China(Technological Sciences)》 SCIE EI CAS CSCD 2021年第9期1940-1946,共7页
A reliable ^(235)U enrichment uniformity detection system based on a compact D–D neutron generator is developed to detect the ^(235)U enrichment uniformity of different fuel elements in the same nuclear fuel rod. The... A reliable ^(235)U enrichment uniformity detection system based on a compact D–D neutron generator is developed to detect the ^(235)U enrichment uniformity of different fuel elements in the same nuclear fuel rod. The high-yield compact D–D neutron generator provides 2.45 MeV D–D neutrons, decelerated by a moderator to thermal neutrons or epithermal neutrons, thereby inducing ^(235)U fission to produce highly excited state fission fragments that undergo de-excitation via γ-ray emission. The system detects the ^(235)U enrichment uniformity of a nuclear fuel rod by measuring γ-rays and establishing a relationship between the γ-ray count rate and ^(235)U enrichment in nuclear fuel. The proposed system yields a confidence probability of 99.99% for a relative ^(235)U enrichment deviation of 10% and a neutron yield of 5 × 10^(8) n/s, and the detection accuracy increases with increasing neutron yield. Furthermore, the developed system can satisfy quality control requirements for nuclear fuel production to promote the safe development of nuclear power. 展开更多
关键词 compact D–D neutron generator ^(235)U enrichment detection BGO crystal
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