钌、碘、氚在动力堆元件溶解和钌在废液蒸发过程中逸出行为的模拟研究  

ANALOGICAL STUDY OF RELEASE OF Ru,I,3H DURING DISSOLVING POWER SPENT FUEL AND RADIOACTIVE LIQUID WASTE EVAPORATION

作　　者：廖元宗[1] 刘淑清[1] 庞合鼎 程明川[2] 张炽光 孙玉珍[2] 

机构地区：[1]中国原子能科学研究院放射化学研究所 [2]北京核工程研究设计院

出　　处：《原子能科学技术》1998年第S1期26-31,共6页Atomic Energy Science and Technology

摘　　要：对钌、碘、氚在元件溶解和废液蒸发过程中的逸出行为进行了模拟研究。结果表明：在试验条件下，钌的逸出量为０．００６％，９９％以上的碘逸出进入溶解尾气，９９．９％的氚留在溶解液中。强放和中放废液蒸发时，钌的逸出量分别为０．００３８％—０．００４８％和０．３４％—０．６８％。he paper describes analogical study of release of Ru, I,　3H during dissolving power reactor spent fuel and Ru in radioactive liquid waste evaporation process. The experimental results show that under the experimental conditions, escaped quantity of Ru is 0.006 %, and 99 % of I2 releases into dissolution offgas, and 99.9 % of 3H remains in solution of dissolving fuel. When evaporating highlevel liquid waste and intermediate level waste, the escaped quantity of Ru is 00038 %—00048 % and 0.34 %—0.68 %, respectively.

关 键 词：乏燃料 溶解 放射性废液 蒸发 逸出 钌 碘 氚 

分 类 号：TL941.12[核科学技术—辐射防护及环境保护]