Recycle of LWR [Light Water Reactor] actinides to an IFR [Integral Fast Reactor]
Description
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
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91007759; NTIS; INIS; US Govt. Printing Office Dep.Files
22052107.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- CONF-910413--1
Conference
- Title
- 3. international conference on nuclear fuel reprocessing and waste management.
- Dates
- 15-18 Apr 1991.
- Place
- Sendai (Japan).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22052107
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; ALLOY NUCLEAR FUELS; ANL; BWR TYPE REACTORS; CAPTURE; DECONTAMINATION; EBR-2 REACTOR; FISSION; FUEL CYCLE; HIGH-LEVEL RADIOACTIVE WASTES; IRRADIATION; LICENSING; PWR TYPE REACTORS; PYROCHEMICAL REPROCESSING; SAFETY; SPENT FUELS; TRANSURANIUM ELEMENTS; URANIUM; URANIUM DIOXIDE; URANIUM RECYCLE; WASTE PROCESSING
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; CLEANING; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; 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; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; REACTORS; REPROCESSING; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; SOLID FUELS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- USDOE, Washington, DC (USA).