Physical properties of an alumino-silicate waste form for cesium and strontium.
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
Similar Records
Engineered Materials for Cesium and Strontium Storage Final Technical Report
Cesium and Strontium Separation Technologies Literature Review
Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
29 ENERGY PLANNING, POLICY, AND ECONOMY
BARIUM
BENTONITE
CESIUM
CLAYS
GASES
NUCLEAR FUELS
NUCLEAR POWER
PHYSICAL PROPERTIES
RECYCLING
REPROCESSING
RUBIDIUM
SILICATES
SINTERING
STRONTIUM
VOLATILITY
WASTE FORMS
WASTES
WATER