核电厂废液处理系统离子交换处理工艺研究  

Research on Ion Exchange Treatment Technology in Liquid Radwaste System of Nuclear Power Plant

作　　者：柳丹[1] 刘杰安[1] 何艳红[1] 王鑫[1] 朱来叶[1] 漏汇 陈斌[1] 翁明辉[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《原子能科学技术》2015年第9期1565-1572,共8页Atomic Energy Science and Technology

基　　金：大型先进压水堆核电站国家科技重大专项资助项目(2010ZX06002)

摘　　要：针对CAP1000系列核电厂废液处理系统(WLS)离子交换工艺树脂选型和运行参数设计开展非放射性环境下树脂运行寿命模拟试验研究。本文从树脂内部结构(交联度/粒径)角度进行选型试验,对运行流速、温度、装填层高等工艺参数造成的树脂工作交换容量差异性进行研究,并从整球率、好球率、压碎强度、体积全交换容量、含水量、TOC释放水平等指标评判辐照对树脂物化稳定性的影响。试验结果显示,高交联度均粒树脂在不同运行工况下表现出交换容量和使用寿命的优异性,工艺设计上优选其进行后续放射性验证试验以实现废物最小化。Simulated experiments in non‐radioactive environment were performed focu‐sing on resin type selection and operating parameters which are major concerned in ion exchange designation in liquid radwaste system of nuclear power plant .In this paper , experiments were made for type selection of resins based on their structures （cross‐linking degree and particle size） ,and the differences of operating capacity caused by technologic parameters （flow rate ,temperature and loading height） were studied .The effect of irradiation on the stability of resin was also evaluated from the performance indicators of whole beads ,whole uncracked beads ,crush strength ,total wet volume capacity ,moisture holding capacity and release level of TOC .The monosphere resin of high cross‐linking degree exhibits excellent exchange capacity and service life under dif‐ferent operating conditions ,and they are prior to be recommended in subsequent radio‐active experiments for engineering design to achieve radwaste minimization .

关 键 词：核电厂 废液处理系统 离子交换 树脂 交换容量 

分 类 号：TL941.19[核科学技术—辐射防护及环境保护] X771[环境科学与工程—环境工程]