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Physical properties of an alumino-silicate waste form for cesium and strontium.

Journal Article · · J. Nucl. Mater.

Nuclear fuel reprocessing will be required to sustain nuclear power as a baseload energy supplier for the world. New reprocessing schemes offer an opportunity to develop a better strategy for recycling elements in the fuel and preparing stable waste forms. Advanced strategies could create a waste stream of cesium, strontium, rubidium, and barium. Some physical properties of a waste form containing these elements sintered into bentonite clay were evaluated. We prepared samples loaded to 27% by mass to a density of approximately 3 g/cm{sup 3}. Sintering temperatures of up to 1000 C did not result in volatility of cesium. Instead, the crystallinity noticeably increased in the waste form as temperatures increased from 600 to 1000 C. Assemblages of silicates were formed. Significant water evolved at approximately 600 C but no other gases were generated at higher temperatures.

Research Organization:
Argonne National Laboratory (ANL)
Sponsoring Organization:
NE
DOE Contract Number:
AC02-06CH11357
OSTI ID:
986288
Report Number(s):
ANL/CSE/JA-63250
Journal Information:
J. Nucl. Mater., Journal Name: J. Nucl. Mater. Journal Issue: 3 ; Aug. 1, 2009 Vol. 392; ISSN 0022-3115
Country of Publication:
United States
Language:
ENGLISH