http://rdf.ncbi.nlm.nih.gov/pubchem/patent/US-7445760-B2

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filingDate 2001-09-07-04:00^^<http://www.w3.org/2001/XMLSchema#date>
grantDate 2008-11-04-04:00^^<http://www.w3.org/2001/XMLSchema#date>
inventor http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_5e380df9c6bab847a0d2f3cd2fc12e00
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publicationDate 2008-11-04-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber US-7445760-B2
titleOfInvention Method of reprocessing spent nuclear fuel
abstract Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to convert the uranium into UF 6 , and the uranium is purified through a simple method of distilling the UF 6 together with a absorbent. After removing the most part of the amount of uranium, the remaining nuclear fuel material is dissolved and then transferred to an extraction process to recover plutonium. By doing so, a small sized dry process can be employed as a uranium purification process. Since the nuclear fuel material is dissolved and extracted after removing most part of an amount of uranium, a volume of processing solution can be reduced and the machine installation scale can be made small. Accordingly, the reprocessing facility can be extremely downsized.
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Total number of triples: 39.