Chop-leach fuel bundle residues densification by melting
Two melting processes were investigated for the densification of fuel bundle residues: Industoslag melting and graphite crucible melting. The Industoslag process, with prior decontamination and sorting, can produce ingots of Zircaloy, stainless steel and Inconel of a quality suitable for refabrication and reuse. The process can also melt oxidized mixtures of fuel bundle residues for direct storage. Eutectic mixtures of these materials can be melted in graphite at temperatures of 1300/sup 0/C. Hydrogen absorption experiments with the zirconium-rich alloys show the alloys to be potential tritium reservoirs. 13 figures.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-1830
- OSTI ID:
- 7322712
- Report Number(s):
- BNWL-2132
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
EUTECTICS
FUEL ASSEMBLIES
FUEL CYCLE
FUEL ELEMENTS
HEAD END PROCESSES
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MELTING
NICKEL ALLOYS
NICKEL BASE ALLOYS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
REPROCESSING
RESIDUES
SEPARATION PROCESSES
SPENT FUEL ELEMENTS
STAINLESS STEELS
STEELS
TIN ALLOYS
WATER COOLED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
EUTECTICS
FUEL ASSEMBLIES
FUEL CYCLE
FUEL ELEMENTS
HEAD END PROCESSES
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MELTING
NICKEL ALLOYS
NICKEL BASE ALLOYS
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
REPROCESSING
RESIDUES
SEPARATION PROCESSES
SPENT FUEL ELEMENTS
STAINLESS STEELS
STEELS
TIN ALLOYS
WATER COOLED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS