http://rdf.ncbi.nlm.nih.gov/pubchem/patent/FR-2840446-A1

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classificationIPCInventive http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46
filingDate 2003-01-03-04:00^^<http://www.w3.org/2001/XMLSchema#date>
inventor http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_08ba8ab3c57b8bd10bf687e432ac48fc
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publicationDate 2003-12-05-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber FR-2840446-A1
titleOfInvention PROCESS FOR THE PROCESSING OF A DEPLETED NUCLEAR FUEL
abstract The invention relates to the reprocessing of spent nuclear fuel. The fuel powder is brought into contact with an extraction agent containing nitric acid to dissolve and extract U and Pu. The agent obtained is brought into contact with nitric acid containing a reducing agent to re-extract Pu and leave U. The resulting nitric acid solution is denitrated to recover Pu in the form of oxide. The extracting agent containing U is brought into contact with nitric acid to re-extract U and the nitric acid obtained containing U is denitrated to recover U in the form of oxide. Application: improved reprocessing comprising a smaller number of steps.
isCitedBy http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-110831681-A
priorityDate 2002-06-04-04:00^^<http://www.w3.org/2001/XMLSchema#date>
type http://data.epo.org/linked-data/def/patent/Publication

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