| Predicate |
Object |
| assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_215310017f1a1bece40da219070d307f
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_99505f5f312672820e9f78c254c00a4d |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02E30-30
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02W30-50 |
| classificationCPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-46
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G43-01
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G43-003
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G56-001
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G56-00 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C01G43-01
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C01G56-00 |
| filingDate |
2006-05-24-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_32c9e5e8e645087c14e3068f4cc84d65
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_138536b1e9803c23253b81b508c52621
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_f78d11358b1f977ce26848b76544abe1
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_fdf00b4251e945c6f294bcdca02e7af7
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_9ee0b3f39264cd01de6d9f550c52b029 |
| publicationDate |
2007-11-30-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
FR-2901627-A1 |
| titleOfInvention |
PROCESS FOR THE REHABILITATION OF USEFUL NUCLEAR FUEL AND THE PREPARATION OF A MIXED OXIDE OF URANIUM AND PLUTONIUM |
| abstract |
The invention relates to a process for the reprocessing of spent nuclear fuel and the preparation of a mixed oxide of uranium and plutonium, which comprises: a) the separation of uranium and plutonium from fission products; americium and curium present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step comprising at least one operation of co-extraction of the uranium and plutonium of said solution with a solvent phase; (b) the distribution of the co-extracted uranium and plutonium into a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium without plutonium, and (c) the purification of plutonium and plutonium. uranium present in the first aqueous phase; andd) a step of co-conversion of plutonium and uranium into a mixed uranium / plutonium oxide.Applications: reprocessing of nuclear fuels based on uranium oxide or mixed uranium and plutonium oxide. |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2456244-C2 |
| priorityDate |
2006-05-24-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |