辐射防护通讯
輻射防護通訊
복사방호통신
RADIATION PROTECTION BULLETIN
2014年
4期
36-38
,共3页
梁栋%闫晓俊%柳兆峰%高超%贾梅兰%安鸿翔
樑棟%閆曉俊%柳兆峰%高超%賈梅蘭%安鴻翔
량동%염효준%류조봉%고초%가매란%안홍상
核素载带%桶内干燥%放射性浓缩液
覈素載帶%桶內榦燥%放射性濃縮液
핵소재대%통내간조%방사성농축액
Nuclides loading%In-drum drying%Radioactive liquid concentrates
在不同温度下对模拟浓缩液进行桶内干燥试验,以研究该干燥方法处理核电站产生的放射性浓缩液尾气中核素的活度浓度及分布。结果表明,107℃(沸腾状态)干燥,Sr、Cs、Co的载带率为5.14%、0.06,0.05%,且大部分在洗涤液中;90℃(非沸腾状态)干燥,Sr、Cs、Co的载带率分别为2.38%、0.03%、0.02%。
在不同溫度下對模擬濃縮液進行桶內榦燥試驗,以研究該榦燥方法處理覈電站產生的放射性濃縮液尾氣中覈素的活度濃度及分佈。結果錶明,107℃(沸騰狀態)榦燥,Sr、Cs、Co的載帶率為5.14%、0.06,0.05%,且大部分在洗滌液中;90℃(非沸騰狀態)榦燥,Sr、Cs、Co的載帶率分彆為2.38%、0.03%、0.02%。
재불동온도하대모의농축액진행통내간조시험,이연구해간조방법처리핵전참산생적방사성농축액미기중핵소적활도농도급분포。결과표명,107℃(비등상태)간조,Sr、Cs、Co적재대솔위5.14%、0.06,0.05%,차대부분재세조액중;90℃(비비등상태)간조,Sr、Cs、Co적재대솔분별위2.38%、0.03%、0.02%。
In-drum drying treatment of simulated concentrates was conducted at variable temperatures to iden-tify the activity concentrations and distribution of nuclides loaded in offgas during treatment of radioactive waste generated from a NPP .The result has shown that there exist detectable contents of Sr ,Cs ,and Co in concen-trated liquid and washing liquid ,with growing decreased activity concentrations with decreased drying tempera-tures .The loading ratios of Sr ,Cs ,and Co are respectively 5 .14% ,0 .06% and 0 .05% under the boiling condition ,mostly in washing liquid ,whereas 2 .38% ,0 .03% and 0 .02% respectively under non-boiling condition .