Radiocesium removal from high level liquid waste and immobilisation in sodium silicotitanate for geological disposal

被引：9

作者：

Tomasberger, T

Veltkamp, AC

Booij, AS

Scherer, UW

机构：

[1] NRG Petten, NL-1755 ZG Petten, Netherlands

[2] Fachhsch Aachen, Abt Julich, D-52428 Julich, Germany

来源：

RADIOCHIMICA ACTA | 2001年 / 89卷 / 03期

关键词：

crystalline sodium silicotitanate (CST); high level liquid waste (HLLW); loading capacity; thermal treatment; MCC-1 leaching test;

D O I：

10.1524/ract.2001.89.3.145

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

The isolation of the fission product cesium from high-level alkaline liquid waste is studied with inorganic ion-exchange materials. High separation and concentration factors can be obtained using sodium silicotitanate (CST). The leaching behaviour of cesium from CST was studied in clay porewater and Quinary brine at 90 degreesC. It is shown that cesium leaching in Quinary brine can be drastically reduced by thermal treatment of cesium loaded CST above 1000 degreesC. To this end, neutralisation of the ion exchange material before heating is required in order to reduce cesium volatility. It is concluded that CST is a good candidate material for geological disposal of the fission product cesium.

引用

页码：145 / 149

页数：5