Chop-leach fuel bundle residues: densification by melting

Conference · Thu Jan 01 04:00:00 EST 1976

OSTI ID:7318484

Nelson, R. G.; Griggs, B.

Two melting processes are presented for the densification of fuel bundle residues. The Inductoslag process, with prior decontamination and sorting, might produce ingots of Zircaloy, stainless steel and Inconel of a quality suitable for refabrication and reuse. The process can also melt oxidized mixtures of residues for direct storage. Eutectic mixtures of these materials can also be melted in graphite at temperatures of 1300/sup 0/C. Hydrogen absorption experiments with the zirconium-containing alloys show them to be potential tritium reservoirs. (12 fig, 21 references)

• Research Organization: Battelle Pacific Northwest Labs., Richland, Wash. (USA)
• DOE Contract Number: E(45-1)-1830
• OSTI ID: 7318484
• Report Number(s): BNWL-SA-5704; CONF-760622-25
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ADSORPTION
ALLOYS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYOGENIC FLUIDS
DECLADDING
ELEMENTS
FLUIDS
FUEL ASSEMBLIES
FUEL CANS
FUEL CYCLE
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
HEAD END PROCESSES
HEAT RESISTING ALLOYS
HYDROGEN
INCONEL 718
INCONEL ALLOYS
IRON ADDITIONS
IRON ALLOYS
IRON BASE ALLOYS
MELTING
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
NONMETALS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
RESIDUES
SORPTION
SORPTIVE PROPERTIES
SPENT FUEL ELEMENTS
STAINLESS STEEL-304
STAINLESS STEEL-304L
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SURFACE PROPERTIES
TIN ALLOYS
WATER COOLED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS