Recycle of LWR (Light Water Reactor) actinides to an IFR (Integral Fast Reactor)

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:6127065

Pierce, R D; Ackerman, J P; Johnson, G K; Mulcahey, T P; Poa, D S

A large quantity of actinide elements is present in irradiated Light Water Reactor (LWR) fuel that is stored throughout the world. Because of the high fission-to-capture ratio for the transuranium (TRU) elements with the high-energy neutrons in the metal-fueled Integral Fast Reactor (IFR), that reactor can consume these elements effectively. The stored fuel represents a valuable resource for an expanding application of fast power reactors. In addition, removal of the TRU elements from the spent LWR fuel has the potential for increasing the capacity of a high-level waste facility by reducing the heat loads and increasing the margin of safety in meeting licensing requirements. Argonne National Laboratory (ANL) is developing a pyrochemical process, which is compatible with the IFR fuel cycle, for the recovery of TRU elements from LWR fuel. The proposed product is a metallic actinide ingot, which can be introduced into the electrorefining step of the IFR process. The major objective of the LWR fuel recovery process is high TRU element recovery, with decontamination a secondary issue, because fission product removal is accomplished in the IFR process. The extensive pyrochemical processing studies of the 1960s and 1970s provide a basis for the design of possible processes. Two processes were selected for laboratory-scale investigation. One is based on the Salt Transport Process studied at ANL for mixed-oxide fast reactor fuel, and the other is based on the blanket processing studies done for ANL's second Experimental Breeder Reactor (EBR-2). This paper discusses the two processes and is a status report on the experimental studies. 5 refs., 2 figs., 2 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6127065
• Report Number(s): CONF-910413-1; ON: DE91007759; TRN: 91-009387
• Resource Relation: Conference: 3. international conference on nuclear fuel reprocessing and waste management, Sendai (Japan), 15-18 Apr 1991
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
MATERIALS RECOVERY
BWR TYPE REACTORS
SPENT FUELS
PWR TYPE REACTORS
PYROCHEMICAL REPROCESSING
ALLOY NUCLEAR FUELS
ANL
CAPTURE
DECONTAMINATION
EBR-2 REACTOR
FISSION
FUEL CYCLE
HIGH-LEVEL RADIOACTIVE WASTES
IRRADIATION
LICENSING
SAFETY
TRANSURANIUM ELEMENTS
URANIUM
URANIUM DIOXIDE
URANIUM RECYCLE
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
CLEANING
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
NUCLEAR REACTIONS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR MATERIALS
REACTORS
RECOVERY
REPROCESSING
RESEARCH AND TEST REACTORS
SEPARATION PROCESSES
SODIUM COOLED REACTORS
SOLID FUELS
URANIUM COMPOUNDS
URANIUM OXIDES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* - Power Reactors
Breeding
052000 - Nuclear Fuels- Waste Management
050800 - Nuclear Fuels- Spent Fuels Reprocessing