氚污染部件干法去污技术  

Dry Decontamination for Tritiated Wastes

作　　者：石正坤[1] 吴涛[1] 但贵萍[1] 谢云[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《核化学与放射化学》2009年第2期125-128,共4页Journal of Nuclear and Radiochemistry

摘　　要：针对核退役工程中存在的大量含氚废物处理问题,利用设计组装的干法去污处理装置对氚污染的金属进行了加热、紫外线、臭氧去污研究。结果表明,升高温度可明显提高去污效果;220℃用365 nm紫外线照射3 h对不锈钢的表面去污效率可达99%;臭氧与加热联合作用更有利于提高去污效率,220℃时去污3 h,臭氧对不锈钢、铝、黄铜的去污效率可达95%以上;而去污完毕经放置后,金属的氚表面活度会有所增加。To aim at decontamination of tritiated wastes, we have developed and fabricated a dry tritium decontamination system, which is designed to reduce tritium surface contamination of various alloy by UV, ozone and heating. The result indicates that the elevation of tempera- ture can obviously improve decontamination effect. With 3 h irradiation by 365 nm UV at 220 ~C, it has a decontamination rate of 99% to stainless steel surface. Ozone can more obviously improve decontamination effect when metal was heated. Ozone has a decontamination effect beyond 95% to stainless steel, aluminum and brass at 220 ℃. Tritium surface concentration of metal has a little increase after decontamination.

关 键 词：氚 去污 紫外线 臭氧 加热 

分 类 号：TL944[核科学技术—辐射防护及环境保护]