测井中子管回收处理过程中氚释放处理方法  

Method and Effectiveness about Tritium from the Process of Waste Well Logging Neutron Generator's Recovery Treating

作　　者：杜阳[1] 刘宁[1] 廖家丽[1] 杨远友[1] 

机构地区：[1]四川大学原子核科学技术研究所辐射物理及技术教育部重点实验室,成都610041

出　　处：《重庆理工大学学报（自然科学）》2013年第5期109-112,共4页Journal of Chongqing University of Technology：Natural Science

基　　金：国家自然科学基金资助项目(20671065)

摘　　要：为提高中子管产品性能,扩展其应用范围,对测井废中子管回收过程的处理方法进行了研究。提出有效的测井中子管氚废气处理方法,并在解体回收工作现场进行了初步应用测试。结果表明：通过应用本方法,每批次解体后氚的排放总量低于3.7×10~7 Bq,可满足现场排放限值要求,避免工作人员的过量氚吸入,有效保障工作人员和环境的安全。The safety of the staff and environment was ensured by the tritium removal method＇s building and test about recovery well logging neutron tubes disintegration in the glove box. Results showed that waste tritium emissions from every batch＇s disintegration was lower than 3.7 × 10^7Bq, emission limit requirement was in keeping with the tritium removal method and the situation of the staff＇s tritium inhaling excessively was prevented at the well logging neutron tube＇s recovery work site.

关 键 词：中子管 回收处理 氚废气 防护性能 

分 类 号：TJ91[兵器科学与技术—武器系统与运用工程]