摘要
核燃料循环利用、反应堆冷却水处理、乏燃料水池净化等核设施运行过程中会产生放射性废树脂。处理放射性废树脂必须考虑系统辐射防护,采用有效的屏蔽措施保护公众及环境安全。根据屏蔽材料的种类和位置,设计三种不同的屏蔽组合方式,计算分析每种方式的屏蔽效果及适用场景,为工程应用提供相关参考。同时,利用SuperMC辐射屏蔽计算软件,以超临界水氧化处理设施为研究对象,计算分析反应容器、树脂研磨装置、废树脂中转罐、增压泵等废树脂流经设备表面剂量率。计算结果表明,无屏蔽时相关设备表面剂量率为22.13~48.64μSv/h,利用铅屏蔽层对表面剂量率较高的设备进行屏蔽防护,屏蔽后满足控制区5μSv/h以下剂量率限值要求。
Radioactive waste resin is generated during the operation of nuclear facilities such as nuclear fuel recycling,reactor cooling water treatment,and spent fuel pool purification.The treatment of radioactive waste resin must consider system radiation protection issues and adopt effective shielding measures to protect public and environmental safety.Design three different shielding combinations based on the type and location of shielding materials,calculate and analyze the shielding effects and applicable scenarios of each method,and provide relevant reference for engineering applications.Meanwhile,using SuperMC radiation shielding calculation software,the surface dose rate of waste resin flowing through equipment such as reactor vessels,resin grinding devices,waste resin transfer tanks,and booster pumps was calculated and analyzed with waste resin treatment facilities as the research object.The calculation results indicate that the surface dose rate of the relevant equipment is 22.13-48.64μSv/h without shielding.The use of a lead shielding layer to shield and protect equipment with higher surface dose rates meets the requirements of a control area of 5μSv/h or less after shielding.
作者
陈耀峰
张天一
韩佳琪
CHEN Yaofeng;ZHANG Tianyi;HAN Jiaqi(CNNC Seventh Research and Design Institute Co.,Ltd.,Taiyuan 030000,China)
出处
《同位素》
CAS
2024年第4期327-331,共5页
Journal of Isotopes
关键词
放射性废树脂
处理设施
表面剂量率
屏蔽计算
radioactive waste resin
treatment facility
surface dose rate
shielding calculation