Ceramic waste form production and development at ANL-West.
Argonne National Laboratory has developed a method to stabilize spent electrolyte salt discarded from electrorefiners (ER) used to treat spent nuclear fuel. The salt is stabilized in a ceramic using a pressureless consolidation technique. The starting material is zeolite 4A which is used as the host for the fission product and actinide rich salt. Glass frit is added to the salt loaded zeolite before processing to act as a binder. The zeolite 4A is converted to sodalite during processing via pressureless consolidation. This process differs from one used in the past that employed a hot isostatic press. Ceramic is created at 925 C and atmospheric pressure instead of the high pressures used in hot isostatic pressing. Process flow sheets, off-gas test results, processing equipment, and leech test results are presented.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 801636
- Report Number(s):
- ANL/ENT/CP-108511; TRN: US0205565
- Resource Relation:
- Conference: ANS 5th Topical Meeting: DOE Spent Nuclear Fuel and Fissile Materials, Charleston, SC (US), 09/17/2002--09/20/2002; Other Information: PBD: 21 Aug 2002
- Country of Publication:
- United States
- Language:
- English
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