Pyroprocessing oxide spent nuclear fuels for efficient disposal
- 1. Argonne National Lab., IL (United States). Chemical Technology Div.
Description
Pyrochemical processing as a means for conditioning spent nuclear fuels for disposal offers significant advantages over the direct disposal option. The advantages include reduction in high-level waste volume; conversion of most of the high-level waste to a low-level waste in which nearly all the transuranics (TRU) have been removed; and incorporation of the TRUs into a stable, highly radioactive waste form suitable for interim storage, ultimate destruction, or repository disposal. The lithium process has been under development at Argonne National Laboratory for use in pyrochemical conditioning of spent fuel for disposal. All of the process steps have been demonstrated in small-scale (0.5-kg simulated spent fuel) experiments. Engineering-scale (20-kg simulated spent fuel) demonstration of the process is underway, and small-scale experiments have been conducted with actual spent fuel from a light water reactor (LWR). The lithium process is simple, operates at relatively low temperatures, and can achieve high decontamination factors for the TRU elements. Ordinary materials, such as carbon steel, can be used for process containment
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95009901; NTIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- ANL--CMT/CP-84354
Conference
- Title
- challenges and initiatives.
- Acronym
- Spent nuclear fuel meeting
- Dates
- 14-16 Dec 1994.
- Place
- Salt Lake City, UT (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26060460
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELECTROREFINING; FLOWSHEETS; LITHIUM CHLORIDES; LITHIUM OXIDES; MOLTEN SALTS; PILOT PLANTS; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; REDUCING AGENTS; SPENT FUELS; URANIUM; URANIUM OXIDES; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALKALI METAL COMPOUNDS; CHALCOGENIDES; CHLORIDES; CHLORINE COMPOUNDS; DIAGRAMS; ELECTROLYSIS; ELEMENTS; ENERGY SOURCES; FUELS; HALIDES; HALOGEN COMPOUNDS; INFORMATION; LITHIUM COMPOUNDS; LITHIUM HALIDES; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; REFINING; SALTS; URANIUM COMPOUNDS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-941207--31.