The management of spent fuel from materials testing reactors in the United Kingdom
Description
Four MTR Reactors, DIDO, PLUTO, DMTR and HERALD have been constructed and operated in the UK. Of these DMTR and HERALD have now been shut down. The spent fuel elements from DIDO and PLUTO are treated by chemical reprocessing at Dounreay to recover the unused U235 and concentrate the fission product activity. All of the fuel from the DMTR reactor has already been reprocessed at Dounreay, whilst the final core from HERALD will be reprocessed soon. After reprocessing the first cycle raffinate, which contains the bulk of the fission products from the spent fuel, is currently stored in high integrity, stainless steel storage tanks which are housed below ground in heavily shielded vaults. A new plant has been constructed at Dounreay which will first neutralize with caustic soda and then immobilize this liquor in cement. The resulting products will then be kept in an engineered store until an intermediate level waste repository is available. The uranyl nitrate product from reprocessing is evaporated and then blended up by the addition of U235. The uranium is then processed at Dounreay to make more MTR fuel, which is recycled to the remaining reactors. In the longer term uncertainty exists over the continued availability and economic viability of reprocessing, particularly if alternative, cheaper sources of fuel are used. The alternative of long term storage of the spent fuel, followed by direct disposal, is therefore being examined as a contingency. A review of the options has concluded that the preferred route would involve the interim storage of the elements in special cans in a cross-flow, natural convection, air-cooled vault. The use of free standing, concrete storage casks to store the fuel would be significantly more expensive and is not favoured. (author). 2 refs, 7 figs
Additional details
Publishing Information
- Imprint Title
- Management of spent fuel from research and prototype power reactors and residues from post-irradiation examination of fuel
- Imprint Pagination
- 146 p.
- Journal Page Range
- p. 15-28.
- Report number
- IAEA-TECDOC--513
Conference
- Title
- Technical committee on the safe management of spent fuel from research reactors, prototype power reactors and fuel from commercial power reactors that has been subjected to post-irradiation examination.
- Dates
- 28 Nov - 1 Dec 1988.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 21003086
- Subject category
- S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CASKS; ENCAPSULATION; MATERIALS TESTING REACTORS; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; REPROCESSING; SPENT FUEL STORAGE; SPENT FUELS; UNITED KINGDOM; WASTE MANAGEMENT
- Descriptors DEC
- CONTAINERS; DEVELOPED COUNTRIES; ENERGY SOURCES; EUROPE; FUELS; IRRADIATION REACTORS; MANAGEMENT; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; STORAGE; WASTE PROCESSING; WASTE STORAGE