Experimental study on cesium immobilization in struvite structures.

Autor: Wagh AS; Environmental Science Division, Argonne National Laboratory, 9700 S. Cass Avenue, IL 60439, USA. Electronic address: asw@anl.gov., Sayenko SY; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine., Shkuropatenko VA; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine., Tarasov RV; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine., Dykiy MP; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine., Svitlychniy YO; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine., Virych VD; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine., Ulybkina ЕА; National Science Center, Kharkov Institute of Physics and Technology, Kharkov, Ukraine.
Jazyk: angličtina
Zdroj: Journal of hazardous materials [J Hazard Mater] 2016 Jan 25; Vol. 302, pp. 241-249. Date of Electronic Publication: 2015 Oct 08.
DOI: 10.1016/j.jhazmat.2015.09.049
Abstrakt: Ceramicrete, a chemically bonded phosphate ceramic, was developed for nuclear waste immobilization and nuclear radiation shielding. Ceramicrete products are fabricated by an acid-base reaction between magnesium oxide and mono potassium phosphate that has a struvite-K mineral structure. In this study, we demonstrate that this crystalline structure is ideal for incorporating radioactive Cs into a Ceramicrete matrix. This is accomplished by partially replacing K by Cs in the struvite-K structure, thus forming struvite-(K, Cs) mineral. X-ray diffraction and thermo-gravimetric analyses are used to confirm such a replacement. The resulting product is non-leachable and stable at high temperatures, and hence it is an ideal matrix for immobilizing Cs found in high-activity nuclear waste streams. The product can also be used for immobilizing secondary waste streams generated during glass vitrification of spent fuel, or the method described in this article can be used as a pretreatment method during glass vitrification of high level radioactive waste streams. Furthermore, it suggests a method of producing safe commercial radioactive Cs sources.
(Copyright © 2015 Elsevier B.V. All rights reserved.)
Databáze: MEDLINE
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