基于同位素中子源的热中子屏蔽性能测试方法研究  

Study on Thermal Neutron Shielding Performance Test Method Based on Isotope Neutron Source

作　　者：肖海玲 文继 张宏俊[1] 熊忠华[1] 帅茂兵[1] XIAO Hai-ling;WEN Ji;ZHANG Hong-jun;XIONG Zhong-hua;SHUAI Mao-bing(China Academy of Engineering Physics,Mianyang 612907,China)

机构地区：[1]中国工程物理研究院材料研究所,绵阳621907

出　　处：《核电子学与探测技术》2022年第4期745-752,共8页Nuclear Electronics & Detection Technology

基　　金：国家国防科工局乏燃料后处理科研专项项目——防中子辐射纤维及复合材料研究。

摘　　要：目前辐射防护材料的热中子屏蔽性能测试还没有建立统一的方法和参考标准。本文利用MCNP计算机模拟程序设计了同位素中子源慢化装置,并基于该装置提出了扣除实验结果中的中高能中子计数贡献的热中子屏蔽性能测试和计算方法。利用该方法对多种高分子化合物制成的辐射防护材料进行了热中子屏蔽性能的测试,实验结果表明,屏蔽性能的测试结果与模拟计算结果符合较好。At present,there are no unified methods and reference standards for the thermal neutron shielding performance test of radiation protective materials.In this paper,a moderating device for isotope neutron source is designed by using MCNP computer simulation program.The test and calculation method of thermal neutron shielding performance deducting the contribution of medium and high energy neutrons in the experimental results is designed based on the device.The device and method are used to test the thermal neutron shielding performance of radiation protective materials made of various polymer compounds.The experimental results illustrate that the test values of shielding performance are in good agreement with the simulation calculation values.

关 键 词：同位素中子源 热中子 慢化装置 屏蔽性能 

分 类 号：TL816[核科学技术—核技术及应用]