Effect of uranium oxide loading on the enthalpy increment (∆H) and heat capacity (Cp) values of modified borosilicate glass for radwaste immobilisation

Author:

Praveena N.,Maji Binoy Kumar,Jena Hrudananda

Publisher

Springer Science and Business Media LLC

Reference16 articles.

1. IAEA. The long term sustainability of radioactive waste: safety and sustainability. IAEA-LTS/RW, Vienna, June;2003.

2. Ojovan MI. Glasses for nuclear waste immobilization. In: WM’07 conference, February 25–March 1, 2007; Tucson, AZ.

3. Boccaccini AR, Bernardo E, Blain L, Boccaccini DN. Borosilicate and lead glass matrix composites containing pyrochlore phases for nuclear waste encapsulation. J Nucl Mater. 2004;327:148–58.

4. Sobolev IA, Dmitriev SA, Lifanov FA, Kobelev AP, Stefanovsky SV, Ojovan MI. Vitrification processes for low, intermediate radioactive and mixed wastes. Glass Technol. 2005;46:28–35.

5. Bates JK, Ellison AJG, Emery JW, Hoh JC. Glass as a waste form for the immobilisation of plutonium. Mater Res Soc Symp Proc. 1996;412:57–64.

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