贫化铀在快堆辐射场中屏蔽性能及辐照释热影响分析  

Shielding Performance and Irradiation Heat Generation Analysis of Depleted Uranium in a Fast Reactor Radiation Field

作　　者：邓理邻[1] 翟梓安 张丽莉 王霜 李文瀚 夏明明 刘汀 黄博琛 温兴坚 魏述平 DENG Lilin;ZHAI Zian;ZHANG Lili;WANG Shuang;LI Wenhan;XIA Mingming;LIU Ting;HUANG Bochen;WEN Xingjian;WEI Shuping(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《现代应用物理》2022年第3期88-94,共7页Modern Applied Physics

基　　金：国家自然科学基金资助项目(11905213,U1967205)。

摘　　要：研究了贫化铀在快堆中子/γ(n/γ)混合场中的综合屏蔽性能及其辐照释热率,作为对比,同时给出了贫化铀在热堆辐射场中的分析结果。采用粒子输运与燃耗耦合程序,研究了中子和γ射线在贫化铀中的衰减规律和贫化铀的活化行为,并与铅的屏蔽计算结果进行比较;分析了贫化铀的辐照释热特性及对屏蔽层温度的影响。结果表明,针对典型快堆n/γ混合场,在本文分析的屏蔽效果指标下,厚度小于16 cm的贫化铀屏蔽层的屏蔽效果都要优于铅。通过对贫化铀辐照释热问题的理论分析得出,贫化铀屏蔽层的辐照释热率高于铅,但对典型核动力反应堆整体屏蔽层温度的影响很小。In this paper,the comprehensive shielding performance and irradiation heat generation rate of depleted uranium in the mixed field of a fast reactor neutron/γ(n/γ)are studied.As a comparison,the analytical results of depleted uranium in the radiation field of thermal reactor are given.The calculation of n/γattenuation in depleted uranium and the activation behavior of depleted uranium are studied by using the coupled program of Monte Carlo particle transport code(MCNP)and the fuel consumption code Origen,and the results are compared with the shielding calculation results of lead.The irradiation heat generation rate characteristics of depleted uranium and its effect on the temperature of shielding layer are analyzed.The results show that the shielding effect of depleted uranium with thickness less than 16 cm is better than that of lead under the shielding effect index analyzed in this paper.The analysis shows that the irradiation heat generation rate of depleted uranium shielding layer is higher than that of lead,which has little effect on the overall shielding layer temperature of typical nuclear power reactor.

关 键 词：贫化铀 屏蔽材料 快堆 屏蔽性能 辐射防护 辐照释热 

分 类 号：TL375[核科学技术—核技术及应用] O571[理学—粒子物理与原子核物理]