放射性固体废物处置场接收^(129)I活度限值研究  

Study on the Activity Limit of ^(129)I Received by Radioactive Solid Waste Disposal Site

作　　者：赵杨军[1] 滕柯延 廉冰[1] 杨洁[1] 王彦[1] ZHAO Yang-jun;TENG Ke-yan;LIAN Bing;YANG Jie;WANG Yan(China Institution for Protection,Taiyuan 030006,China;Nuclear&Radiation Safety Center,Beijing 100082,China)

机构地区：[1]中国辐射防护研究院,太原030006 [2]生态环境部核与辐射安全中心,北京100082

出　　处：《四川环境》2023年第2期165-169,共5页Sichuan Environment

摘　　要：我国核能事业的快速发展会产生大量的含^(129)I废物需要处置,根据龙和低放固体废物近地表处置场周围自然环境条件和水文地质资料,对该处置场正常演化、钻探以及钻探后景象进行研究,采用IAEA推荐的活度限值研究方法,对处置场接收处置废物中的129I活度限值进行研究,推荐龙和处置场接收废物中的^(129)I活度限值为9.01×10^(10)Bq,能够满足核能发展过程中含^(129)I废物的处置需求。With the development of nuclear energy industry,a large amount of radioactive waste containing^(129)I will be produced and need to be disposed of.This paper based on the environmental conditions and hydrogeological data around the Long He LILW repository,studied the normal evolution scenario,drilling scenario and after drilling scenario of the site.Adopting the activity limit method recommended by IAEA,the upper limit value of^(129)I activity in disposed by each scenario under the dose criterion was studied.It is recommended that the activity limit of^(129)I in Long He LILW repository is 9.01×10^(10)Bq,which can meet the waste disposal needs in the process of nuclear energy development.

关 键 词：处置场 活度限值 废物处置 碘-129 

分 类 号：TL942[核科学技术—辐射防护及环境保护]