辐射防护 ›› 2015, Vol. 35 ›› Issue (4): 204-208.

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FCTC10型工业辐照60Co运输容器屏蔽测量与评价

李国强1, 庄大杰1, 孙洪超1, 罗晓渭1, 杨哲2, 王盼2   

  1. 1.中国辐射防护研究院,太原 030006;
    2.中核同兴(北京)核技术有限公司,北京 100045
  • 收稿日期:2014-12-23 出版日期:2015-07-20 发布日期:2024-10-21
  • 作者简介:李国强(1975—),男,2004年毕业于广西大学理论物理专业,获硕士学位,2012年毕业于中国原子能科学研究院辐射防护及环境保护专业,获博士学位。E-mail:liguoqiang@cirp.org.cn

Shielding performance measurement and assessment for FCTC10 industrial cobalt-60 transport container

Li Guoqiang1, Zhuang Dajie1, Sun Hongchao1, Luo Xiaowei1, Yang Zhe2, Wang Pan2   

  1. 1. China Institute for Radiation Protection, Taiyuan 030006;
    2. Tongxing (Beijing) Nuclear Technology Co. Ltd., CNNC, Beijing 100045
  • Received:2014-12-23 Online:2015-07-20 Published:2024-10-21

摘要: FCTC10型容器设计用于装载工业辐照60Co源,在装载18万居里(Ci) 60Co放射源时属B(U)型、Ⅲ级(黄)货包。FCTC10型容器由屏蔽容器、吊篮、防护罩与运输托架组成,主要利用屏蔽容器主体和铅塞的钢壳层及其中间填充的钨合金、铅屏蔽层实现货包的屏蔽功能。采用蒙特卡罗方法模拟计算和实验测量相结合的方法给出FCTC10运输容器在满载时的辐射水平,结果表明FCTC10容器满足GB 11806—2004对货包辐射水平的规定。根据运输实践经验假设了工作人员和公众的受照情景,计算出的单次运输工作人员和公众的受照剂量小于设计考虑的剂量约束值,也低于GB 18871—2002对工作人员和公众的剂量限值。在设计基准事故情况下,容器外部局部区域辐射水平增加量不超过1倍,对事故处理人员的剂量很小。

关键词: 工业辐照, 放射源, 运输容器, 屏蔽, 测量与评价

Abstract: FCTC10 container is designed to transport cobalt-60 radioactive sources used in irradiation industry. It belongs to type B (U) grade Ⅲ (yellow) package when being loaded with a cobalt-60 source of 180 thousands curie. The container is constituted by shielding container, basket, protective cover, and bracket. Shielding ability is provided mainly by stainless steel shells, tungsten alloy and lead among steel shells. Radiation level around the container with maximum load are given through both Monte Carlo method simulation calculation and experiment measurement. It is proven that the shielding performance of the container is complied with the requirements in GB 11806—2004. Exposure doses of workers and public key groups are given based on hypothetical exposure scene according to transport practice experience. The results show that exposure doses of the workers and the public are less than the constraint dose considered in design, and also lower than dose limit regulated in GB 18871—2002. The dose received by the responders will be small becouse the increase of radiation level outside the container is tess than one time under design basis accidents.

Key words: irradiation industry, radioactive source, transport container, shielding, measurement and assessment

中图分类号: 

  • TL93+2.1