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Process considerations for hot pressing ceramic nuclear waste forms

Conference ·
OSTI ID:6468562
;
Spray calcined simulated ceramic nuclear waste powders were hot pressed in graphite, nickel-lined graphite and ZrO/sub 2/-lined Al/sub 2/O/sub 3/ dies. Densification, initial off-gas, waste element retention and pellet-die interactions were evaluated. Indicated process considerations and limitations are discussed. 15 figures.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA); Battelle Pacific Northwest Labs., Richland, WA (USA)
DOE Contract Number:
AC14-76FF02170
OSTI ID:
6468562
Report Number(s):
HEDL-SA-2235; CONF-810528-7; ON: DE81023183
Country of Publication:
United States
Language:
English

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Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
CHALCOGENIDES
CHEMICAL REACTIONS
CRYSTAL STRUCTURE
DEPOSITION
DIES
EXPANSION
FABRICATION
HOT PRESSING
MANAGEMENT
MATERIALS WORKING
MICROSTRUCTURE
MOLDING
OXIDES
OXYGEN COMPOUNDS
PELLETIZING
PELLETS
PRESSING
PROCESSING
RADIOACTIVE WASTE PROCESSING
SPRAY COATING
SURFACE COATING
THERMAL EXPANSION
TRANSITION ELEMENT COMPOUNDS
WASTE MANAGEMENT
WASTE PROCESSING
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES