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classificationIPCInventive http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C01G56-00
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46
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filingDate 1999-09-07-04:00^^<http://www.w3.org/2001/XMLSchema#date>
grantDate 2000-06-05-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationDate 2000-06-05-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber JP-3049320-B1
titleOfInvention Plutonium separation and recovery method
abstract An object of the present invention is to provide a method for efficiently separating and recovering plutonium from spent nuclear fuel, waste liquid generated in a nuclear-related facility, and waste or waste liquid generated in a process of producing or dismantling nuclear materials by an easy operation. SOLUTION: After a plutonium-containing nitric acid or nitrate solution is brought into contact with an anion exchanger to partially or entirely adsorb plutonium as a nitrate ion complex, an acid solution having a weak ability to form a complex with plutonium is used as an eluent. A method for separating and recovering plutonium, comprising selectively eluting and recovering adsorbed plutonium used as a catalyst.
isCitedBy http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-111863300-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2023155278-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-114686709-A
priorityDate 1999-09-07-04:00^^<http://www.w3.org/2001/XMLSchema#date>
type http://data.epo.org/linked-data/def/patent/Publication

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