Retention of some hazardous radionuclides from nitric acid solution using tin(IV) antimonate as a cation exchanger

被引：4

作者：

El-Dessouky, MI ^{[1
]}

El-Dessouky, SI ^{[1
]}

Abou-Mesalam, MM ^{[1
]}

机构：

[1] Atom Energy Author, Hot Labs Ctr, Cairo, Egypt

来源：

RADIOCHIMICA ACTA | 2000年 / 88卷 / 02期

关键词：

liquid waste; cation exchanger; removal; capacity; solidification; leaching;

D O I：

10.1524/ract.2000.88.2.101

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

The removal of some hazardous radioactive nuclides such as Cs+, Co2+, Sr2+ and/or Eu3+ from radioactive liquid waste was carried out either by chemical in-situ precipitation or by using a preformed precipitate of tin(TV) antimonate (SnSb). Stability of the product material for the chemical reagents was investigated at various concentrations of nitric and hydrochloric acids. Capacity and selectivity patterns for CS+, CO2+, Sr2+ and Eu3+ were determined on these matrices. Conditioning of the exhausted tin(IV) antimonate in cement matrix was carried out with the study of some important parameters affecting the properties of the solidified waste forms such as, the compressive strength and the leaching coefficient of these nuclides from the solidified waste form. The leaching coefficient of radioactive nuclides precipitated in-situ with SnSb are smaller than those adsorbed on SnSb or plain ordinary portland cement.

引用

页码：101 / 105

页数：5

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