某型乏燃料运输容器中子辐射屏蔽性能检测

Abstract

Abstract: The radiation shielding performance measurements of transport container is the important content to ensure transportation safety of radioactive material. The radiation shielding performance of radioactive material package must meet the requirements of “Regulations for the safe transport of radioactive material” (GB 11806—2004). However, some of the problems and difficulties reflected in practice need to be solved, such as the measurement results of neutron radiation level of container outer are not always reliable. In this paper,the monitoring results of using both the neutron multi-sphere spectrometer and portable neutron measurement instrument are compared, and the MCNP runs are done to study the shielding performance measurements of spent fuel package. The results of monitoring and simulation are compared, some factors are discussed, and an optimized scheme is recommended.

Key words: radioactive materials transport package, spent fuel, neutron radiation monitoring, MCNP, shielding performance measurements

CLC Number:

R144

Sun Hongchao, Li Guoqiang, Zhuang Dajie, Wang Renze, Sun Shutang, Meng Dongyuan, Wang Xuexin, Zhang Jiangang, Cao Fangfang, Zhang Hongjian. Research on shielding performance measurements of a spent fuel transportation container[J].RADIATION PROTECTION, 2016, 36(5): 317-321.

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Research on shielding performance measurements of a spent fuel transportation container

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