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

Citation
T. Tomasberger et al., Radiocesium removal from high level liquid waste and immobilisation in sodium silicotitanate for geological disposal, RADIOCH ACT, 89(3), 2001, pp. 145-149
Citations number
18
Categorie Soggetti
Inorganic & Nuclear Chemistry
Journal title
RADIOCHIMICA ACTA
ISSN journal
00338230 → ACNP
Volume
89
Issue
3
Year of publication
2001
Pages
145 - 149
Database
ISI
SICI code
0033-8230(2001)89:3<145:RRFHLL>2.0.ZU;2-Y
Abstract
The isolation of the fission product cesium from high-level alkaline liquid waste is studied with inorganic ion-exchange materials. High separation an d 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 materi al before heating is required in order to reduce cesium volatility. It is c oncluded that CST is a good candidate material for geological disposal of t he fission product cesium.