Chemical decontamination and melt densification. [Chop-leach fuel hulls]
Conference
·
OSTI ID:7352047
Preliminary studies on the chemical decontamination and densification of Zircaloy, stainless steel, and Inconel undissolved residues remaining after dissolution of the UO/sub 2/--PuO/sub 2/ spent fuel material from sheared fuel bundles are reported. The studies were made on cold or very small samples to demonstrate the feasibility of the processes developed before proceeding to hot cell demonstrations with kg level of the sources. A promising aqueous decontamination method for Zr alloy cladding was developed in which oxidized surfaces are conditioned with HF prior to leaching with ammonium oxalate, ammonium citrate, ammonium fluoride, and hydrogen peroxide. Feasibility of molten salt decontamination of oxidized Zircaloy was demonstrated. A low melting alloy of Zircaloy, stainless steel, and Inconel was obtained in induction heated graphite crucibles. Segregated Zircaloy cladding sections were directly melted by the inductoslag process to yield a metal ingot suitable for storage. Both Zircaloy and Zircaloy--stainless steel--Inconel alloys proved to be highly satisfactory getters and sinks for recovered tritium. (JSR)
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-1830
- OSTI ID:
- 7352047
- Report Number(s):
- BNWL-SA-5696; CONF-760310-5
- Country of Publication:
- United States
- Language:
- English
Similar Records
Chop-leach fuel bundle residues: densification by melting
Chop-leach fuel bundle residues densification by melting
Cladding hull decontamination and densification process. Part 2. Densification by inductoslag melting
Conference
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7318484
Chop-leach fuel bundle residues densification by melting
Technical Report
·
Sun Oct 31 23:00:00 EST 1976
·
OSTI ID:7322712
Cladding hull decontamination and densification process. Part 2. Densification by inductoslag melting
Technical Report
·
Mon Mar 31 23:00:00 EST 1980
·
OSTI ID:5399415
Related Subjects
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
052001* -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CLEANING
CORROSION RESISTANT ALLOYS
DECONTAMINATION
FUEL CANS
FUEL ELEMENTS
HYDROGEN ISOTOPES
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MANAGEMENT
MELTING
NICKEL ALLOYS
NICKEL BASE ALLOYS
NUCLEI
ODD-EVEN NUCLEI
PHASE TRANSFORMATIONS
RADIOACTIVE WASTE STORAGE
RADIOISOTOPES
REACTOR COMPONENTS
REPROCESSING
SEPARATION PROCESSES
SPENT FUEL ELEMENTS
STAINLESS STEELS
STEELS
STORAGE
TIN ALLOYS
TRITIUM
WASTE MANAGEMENT
WASTE STORAGE
YEARS LIVING RADIOISOTOPES
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
052001* -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CLEANING
CORROSION RESISTANT ALLOYS
DECONTAMINATION
FUEL CANS
FUEL ELEMENTS
HYDROGEN ISOTOPES
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MANAGEMENT
MELTING
NICKEL ALLOYS
NICKEL BASE ALLOYS
NUCLEI
ODD-EVEN NUCLEI
PHASE TRANSFORMATIONS
RADIOACTIVE WASTE STORAGE
RADIOISOTOPES
REACTOR COMPONENTS
REPROCESSING
SEPARATION PROCESSES
SPENT FUEL ELEMENTS
STAINLESS STEELS
STEELS
STORAGE
TIN ALLOYS
TRITIUM
WASTE MANAGEMENT
WASTE STORAGE
YEARS LIVING RADIOISOTOPES
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS