针对车载D-D加速器中子源的紧凑、轻量化屏蔽材料优化设计研究  

Study on Optimization Design of Compact and Lightweight Radiation Shielding Material for Vehicle-mounted Accelerator-driven D-D Neutron Source

作　　者：蔡垚 胡华四[1] 潘紫姮 路双莹 孙伟强 CAI Yao;HU Huasi;PAN Ziheng;LU Shuangying;SUN Weiqiang(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;China Ship Development and Design Center,Wuhan 430064,China)

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049 [2]中国舰船研究设计中心,湖北武汉430064

出　　处：《原子能科学技术》2018年第4期715-721,共7页Atomic Energy Science and Technology

基　　金：陕西省自然科学基础研究计划重点项目资助(2015JZ001)

摘　　要：为减小D-D加速器中子源的体积和质量,本文结合遗传算法和MCNP程序建立了一种针对快中子的优化设计紧凑、轻量化屏蔽材料的方法。基于此方法,设计得到了一系列材料样本,采用MCNP程序模拟了各材料对D-D中子的屏蔽性能,并与传统材料PB202、PE-30%B、M-L1、M-L2进行了对比。为直观比较屏蔽材料的性能,假设加速器生物屏蔽体为同轴渐缩圆柱体结构,对不同材料所需体积及质量进行了对比,结果显示,SDGa性能较好,可同时满足紧凑化与轻量化的需求。同时,对SDG3和SDG3*辐照1 000h后的活化伽马剂量率进行了评估,结果显示其活化影响可忽略。To minimize the size and weight of the vehicle-mounted accelerator-driven D-D neutron source,optimization of compact and lightweight radiation shielding material for the fast neutrons was carried out,which employed genetic algorithms and the MCNP code.Based on this method,a series of material samples were designed and the shielding performance was compared with that of traditional materials such as PB202,PE-30%B,M-L1 and M-L2 for the D-D neutron by MCNP.To compare the shielding performance conveniently,both of the needed volume and weight were compared while assuming the shielding as a coaxial tapered cylinder.The results show that the SDG a can satisfy the requirements of lightweight and compact simultaneously.At the same time,the activation gamma dose rates of SDG3 and SDG3*after 1 000 h irradiation were evaluated,and the results show that the activation can be neglected.

关 键 词：中子 屏蔽 优化 紧凑、轻量化材料 

分 类 号：TL77[核科学技术—辐射防护及环境保护]