The application of electrorefining for recovery and purification of fuel discharged from the Integral Fast Reactor

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:6434958

Burris, L; Steunenberg, R K; Miller, W E

An electrorefining process employing a molten salt electrolyte and a molten cadmium anode is proposed for the separation of uranium and plutonium from fission products and cladding material in discharged IFR driver fuel. The use of a liquid cadmium anode, which is the unique feature of the process, permits selective dissolution of the fuel from the cladding and prevents electrolytic corrosion of the steel container and contamination of the product by noble metal fission products.

• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6434958
• Report Number(s): CONF-861146-; TRN: 87-023209
• Resource Relation: Conference: AIChE winter annual meeting, Miami, FL, USA, 2 Nov 1986
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
ELECTROREFINING
ELECTROLYTES
FAST REACTORS
FISSION PRODUCTS
SEPARATION PROCESSES
PLUTONIUM
MATERIALS RECOVERY
URANIUM
ANODES
CADMIUM
CONTAINERS
CONTAMINATION
CORROSION RESISTANCE
DISSOLUTION
ELECTROCHEMICAL CORROSION
FUEL-CLADDING INTERACTIONS
MOLTEN SALTS
RADIATION PROTECTION
RADIOACTIVE WASTE PROCESSING
STEELS
ACTINIDES
ALLOYS
CHEMICAL REACTIONS
CORROSION
ELECTRODES
ELECTROLYSIS
ELEMENTS
EPITHERMAL REACTORS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LYSIS
MANAGEMENT
MATERIALS
METALS
PROCESSING
RADIOACTIVE MATERIALS
REACTORS
RECOVERY
REFINING
SALTS
TRANSURANIUM ELEMENTS
WASTE MANAGEMENT
WASTE PROCESSING
052001* - Nuclear Fuels- Waste Processing
360105 - Metals & Alloys- Corrosion & Erosion