Developments in reprocessing technology for high-temperature and fast breeder fuels
- 1. Oak Ridge National Lab., Tenn. (USA)
Description
In the United States, comprehensive long-range programs to develop fuel cycle technology for High-Temperature Gas-Cooled Reactors (HTGR) and Liquid Metal Fast Breeder Reactors (LMFBR) are being planned and implemented. In each case, the fuel cycle is an essential integral part of the power reactor system, and the technical problems in the fuel cycle are being solved in parallel with the reactor development program. For the LMFBR, the end point of the technical development will be a demonstration in a hot pilot plant to be operated with fully irradiated fuels from the Clinch River Breeder Reactor (CRBR) in the late 1980s. The program is presently addressing process R and D problems, equipment development, and conceptual design of the pilot plant. The basic process will use a modified chop-leach head-end followed by Purex solvent extraction cycles. Although a large base of experience will come from the early LWR plants, the significant differences between LMFBR and LWR fuels - sodium contamination, more complex fuel hardware, higher fissile and fission product content - introduce new problems requiring substantial development work. Increasing public concern and more stringent emission limits have prompted considerable effort directed toward the retention of the gaseous fission products. For the HTGR, development is directed primarily toward the 233U-Th fuel cycle with a final goal of operation of an HTGR Fuel Recycle Demonstration Facility that can support the recycle requirements of 20 GW(e) installed capacity. The reference fuel element is a prismatic graphite block containing coated fissile and fertile particles bound together by a carbon matrix. Start up is with 235U, which is replaced on subsequent cycles with the bred 233U. Spent fuel elements are crushed and burned, and the fuel particle oxides are dissolved and processed by solvent extraction. Refabrication must be done remotely because of gamma activity from 232U daughters, and the program includes extensive development of the specialized equipment for forming and coating particles, preparation of fuel rods, and assembly of the elements
Availability note (English)
MF available from INIS under the Report Number.Files
8302950.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- IAEA-CN--36/14
Conference
- Title
- International conference on nuclear power and its fuel cycles.
- Dates
- 2 - 13 May 1977.
- Place
- Salzburg, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 8302950
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HTGR TYPE REACTORS; LMFBR TYPE REACTORS; REPROCESSING; SPENT FUEL ELEMENTS; SPENT FUELS
- Descriptors DEC
- BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES
Optional Information
- Notes
- 2.7.-.T.1./12.