^(90)Sr同位素电池放射源的设计模拟与辐射优化  

Design Simulation and Radiation Optimization of ^(90)Sr Isotope Generator Radioactive Source

作　　者：杨立群 贾楠楠 周剑 李叶凡 唐军 YANG Liqun;JIA Nannan;ZHOU Jian;LI Yefan;TANG Jun(The 404 Company Limited,CNNC,Lanzhou 732850,China)

机构地区：[1]中核四○四有限公司,兰州732850

出　　处：《同位素》2024年第1期49-54,共6页Journal of Isotopes

基　　金：甘肃省科技重大专项计划资助项目(No.22ZD6GB020)。

摘　　要：^(90)Sr具有较强的轫致辐射,在制备同位素放射源前,需要先模拟^(90)SrTiO_(3)陶瓷芯块的组分,设计热源盒的结构,并根据制造工艺对芯块、热源包壳进行轫致辐射评估。为了减少热电转换器件的受照剂量,本研究根据β射线的屏蔽原理,提出使用铝箔包裹芯块、优化芯块配料和增加氮化硼垫片的三种降低放射源轫致辐射的方法。MCNP模拟结果显示,三种方法都能有效降低轫致辐射。三种方法均会改变热源盒设计尺寸,且包裹铝箔的方法工程可行性较差。以上结果可为^(90)Sr温差热电池热源部分的设计与制造提供参考,并为电池的辐射优化提供理论方法。^(90)Sr has strong bremsstrahlung radiation,before manufacturing the radioisotope heat source,it is necessary to first simulate the composition of the ^(90)SrTiO_(3) ceramic pellet,design the structure of the fuel cladding,and evaluate the bremsstrahlung radiation of the pellet and fuel cladding according to the manufacturing process.In order to reduce the exposure dose of thermoelectric conversion devices,the article based onβshielding principle has proposed three methods to reduce bremsstrahlung radiation from radioactive sources.The MCNP simulation results show that using aluminum foil to wrap the core blocks,optimizing the core block ingredients,and adding boron nitride gaskets can effectively reduce bremsstrahlung.All three methods will change the design size of the fuel cladding,and the engineering feasibility of wrapping aluminum foil is poor.The research results will guide the design and manufacturing of the source part of the Sr-90 thermoelectric generator,and provide theoretical methods for radiation optimization of the generator.

关 键 词：同位素放射源 MCNP 轫致辐射 ^(90)SrTiO_(3) 热源包壳 

分 类 号：TL7[核科学技术—辐射防护及环境保护] TL929