Gas-fluoride technology for processing spent oxide fuel

The scientific-research work on reprocessing spent oxide fuel by gas-fluoride method is reviewed. The refining possibilities of the basic stages of gas-fluoride technology are studied. The possibility of separating most fission products from the ashes at the fluoridation stage is confirmed experimen...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2001-03, Vol.90 (3), p.224-234
Main Authors: SHATALOV, V. V, SEREGIN, M. B, KHARIN, V. F, PONOMAREV, L. A
Format: Article
Language:English
Subjects:
Applied sciences
Energy
Exact sciences and technology
Fluorides
Fuels
Nuclear fuels
Preparation and processing of nuclear fuels
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Summary:The scientific-research work on reprocessing spent oxide fuel by gas-fluoride method is reviewed. The refining possibilities of the basic stages of gas-fluoride technology are studied. The possibility of separating most fission products from the ashes at the fluoridation stage is confirmed experimentally. The use of fluoride sorbents (NaF, BaF^sub 2^) permits reaching a total coefficient of removal of fission products from UF^sub 6^ at the 10^sup 7^ level. It is shown that deep extraction of plutonium from oxide fuel is possible. The results of investigations on pyrohydrolysis of UF^sub 6^ and a mixture of UF^sub 6^ with PuF^sub 6^ with production of granulate of the oxides with the required density with fluorine content 0.005 mass % and oxygen coefficient 2-2.1 are presented. Recommendations for use of gas-fluoride technology for reprocessing spent oxide fuel from fast and light-water reactors are given taking account of the new requirements for nonproliferation of fissioning materials, and a prediction is given for a closed nuclear fuel cycle using gas-fluoride technology and separation of Np, Am, and Cm for transmutation with the aid of easily melting fluoride melts. 1 figure, 5 tables, 27 references.[PUBLICATION ABSTRACT]
ISSN:1063-4258
1573-8205
DOI:10.1023/A:1011376412282