Experimental study on cesium immobilization in struvite structures

• Published in: Journal of hazardous materials 2016-01, Vol.302 (C), p.241-249
• Main Authors: Wagh, Arun S., Sayenko, S.Y., Shkuropatenko, V.A., Tarasov, R.V., Dykiy, M.P., Svitlychniy, Y.O., Virych, V.D., Ulybkina, Е.А.
• Format: Article
• Language: English
• Subjects: Ceramicrete; Ceramicretea; Cesium immobilization; Chemically bonded phosphate ceramic; INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY; Struvite; Vitrification
• ISSN: 0304-3894; 1873-3336
• DOI: 10.1016/j.jhazmat.2015.09.049

X-ray diffraction patterns of Ceramicrete forms, green representing struvite-K, and red, struvite-(K,Cs) with 10wt.% CsCl in it. Cs substitutes partially for K, which immobilizes Cs at room temperature by the acid–base reaction. [Display omitted] •Struvite structure of Ceramicrete is an excellent host of radioactive cesium.•The volatility problem of cesium can be avoided by this method.•This method can be used to produce cesium waste forms in ambient conditions.•It can also be used to pretreat cesium in glass vitrification technology.•It also provides a method to produce safe sealed radioactive sources of cesium. 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.