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Title	Ceramic waste form production and development at ANL-West.
Creator/Author	Battisti, T. J. ; Goff, K. M. ; Bateman, K. J. ; Simpson, M. F. ; Lind, J. P.
Publication Date	2002 Aug 21
OSTI Identifier	OSTI ID: 801636
Report Number(s)	ANL/ENT/CP-108511
DOE Contract Number	W-31-109-ENG-38
Other Number(s)	TRN: US200223%%310
Resource Type	Conference
Resource Relation	ANS 5th Topical Meeting: DOE Spent Nuclear Fuel and Fissile Materials, Charleston, SC (US), 09/17/2002--09/20/2002 ; PBD: 21 Aug 2002
Research Org	Argonne National Lab., IL (US)
Sponsoring Org	US Department of Energy (US)
Subject	11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES ; ACTINIDES; ATMOSPHERIC PRESSURE; CERAMICS; ELECTROLYTES; FISSILE MATERIALS; FISSION PRODUCTS; FLOWSHEETS; NUCLEAR FUELS; PRESSING; WASTE FORMS; ZEOLITES
Description/Abstract	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.
Country of Publication	United States
Language	English
Format	8 pages ; PDFN
System Entry Date	2002 Dec 16
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