摘要
针对贫化铀的γ射线屏蔽进行了实验与模拟计算验证。构建了核动力压水堆屏蔽模型,模拟输出的屏蔽层内中子能谱与实际能谱分布较为一致。采用蒙特卡罗程序与燃耗计算程序相耦合的方法,模拟计算了贫化铀在不同位置处中子、γ混合辐射场中的综合屏蔽性能,并与铅作为屏蔽材料进行了对比分析。模拟计算了屏蔽层中子辐照贫化铀40 a后的活化和裂变产物,分析了材料辐照前后年摄入量限值(ALI)定义下的放射性毒性,结果表明,新增二次产物对放射性毒性影响不大。
In this paper, the gamma ray shielding of depleted uranium is verified by experiment and simulation. A nuclear power pressurized water reactor shielding model is constructed, and the simulation distribution of neutron energy spectrum in the shielding layer was consistent with that in practice. The comprehensive shielding performance of depleted uranium in different positions of neutron and gamma mixed radiation field were simulated by the Monte Carlo simulation method and the fuel consumption calculation program, and compared with that of the lead shielding material. The activation and fission products of the depleted uranium irradiated by the shielding neutrons for 40 a was simulated and calculated, and the radio-toxicity defined by Annual Limit of Intake(ALI) before and after irradiation of the material was analyzed. The results show that the addition of secondary products has little effect on the radio-toxicity.
作者
宋英明
王岩
肖锋
吕焕文
付孟婷
沈格宇
Song Yingming;Wang Yan;Xiao Feng;Lyu Huanwen;Fu Mengting;Shen Geyu(School of Nuclear Science and Technology,University of South China,Hengyang,Hunan,421001,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第6期173-177,共5页
Nuclear Power Engineering
基金
装备预先研究项目（NO.32102040505）
核燃料循环技术与装备湖南省协同创新中心开放基金项目(NO.2019KFQ14)
关键词
贫化铀
核动力堆
屏蔽性能
放射性毒性
Depleted uranium
Nuclear power reactor
Shielding effectiveness
Radio-toxicity
