利用无机离子交换剂从碱性澄清液中除去^(137)Cs和^(90)Sr的研究

REMOVAL OF CESIUM AND STRONTIUM FROM ALKLINE RADIOACTIVE SUPERNATE WITH INORGANIC ION EXCHANGER

本文的实验结果表明:沸石串联柱,对^(137)Cs的去污因素达到1000,浓缩倍数可达到500.钛酸钠交换柱,对^(90)Sr的去污因素为1000时,浓缩倍数为1800.负载^(137)Cs的沸石和负载^(90)Sr的钛酸钠在900℃下煅烧,失去交换性能,可作为固体废物贮存,也可直接与水泥渗合,固化,本法处理碱性放射性废水澄清液,对Cs和Sr的去污因素和浓缩倍数都比较高,可减少最终贮存固体废物的体积,降低Cs,Sr在水泥中的渗出,对安全贮存放射性固体废物是有利的.

A process for separating of ^(137)Cs and ^(90)Sr from alkline radioactive superuate by zeolite and titanate was established. Tracer-level studies showed that zeolite and titanate efficiently sorbed cesium and strontium from synthetic waste. In column tests using synthetic waste, >99.9% of ^(137)Cs was removed. ^(137)Cs was eluted from the zeolite column by 2M(NH_4)_2CO_3 + 2MNH_4OH.^(137)Cs sorbed on insoluble ferrocyanides for final solidification in concrete or glass and as a ^(137)Cs source looks possible. From the results of four cycles a zeolite column series give DF for ^(137)Cs 1000 and CF 500. Titanate efficiently sorbed strontium directly from synthetic radioactive waste, the DF for ^(90)Sr is 1000 and CF1800. Titanate can be solidified in concerte or glass for final disposal.