靶件内中子注量率分布计算方法研究  

Research on methods for distribution of neutron flux in the experiment target

作　　者：陈炜[1] 杨锐[1] 胡志勇[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《核电子学与探测技术》2007年第2期313-316,共4页Nuclear Electronics & Detection Technology

摘　　要：选择ANISN作为实验靶件内中子注量率分布计算的程序,编制辅助程序输入混合材料截面。计算得到延时水箱附近的中子注量率,与测量数据作对比。计算得到靶片自屏因子,并与2000年实验数据对比。确认计算方法可行后,计算得到实验靶件内热中子注量率分布数据。ANISN is chosen as the program for the calculation of distribution of nurtron flux in the experiment target in the light of furture experiment trait. A program is developed to make the data describing mixed material. The neutron flux data near external frame and delayed tank in the reactor have been calculated. After comparing with the data measured, it can be said that those data calculated are believable. The factors of self shield of the target flakes have been calculated. After comparing with the data measured, it is thought that those factors calculated are believable. The distribution of flux data in the target got by calculated are the theoretical basis of the furture experiment.

关 键 词：靶件 中子注量率 计算方法 

分 类 号：TL329.2[核科学技术—核技术及应用]