| Predicate |
Object |
| assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_a4d02db04ffddd8a36b020d51e6e8d34
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_99505f5f312672820e9f78c254c00a4d |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02W30-50
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02E30-30 |
| classificationCPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-46
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B60-026
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B3-32 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46 |
| filingDate |
2016-07-28-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_e22e0ac034e00bd8ae96c5cdf975acc0
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_bbbada8791799e5f349818e78213a830
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_1cccc53f0e967824882b75999fa6f90d
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_33dd7e4305377edc074e5d36b80d34ce
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_5375cb090e2d5a969243b1428711fe94
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_4e02835968e22c743309258ae0309897
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_68610148174b2d06c93231d72a2ed74e
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_b0ed0a8c77dde7b5490746a32c84d4b9 |
| publicationDate |
2017-02-02-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
WO-2017017207-A1 |
| titleOfInvention |
Method for the treatment of an aqueous nitric solution used resulting from dissolving spent nuclear fuel, said method being performed in a single cycle and without requiring any operation involving the reductive back-extraction of plutonium |
| abstract |
The invention relates to a method for the treatment of an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any operation involving the reductive back-extraction of the plutonium. The invention is intended for the treatment of spent nuclear fuel comprising uranium and/or plutonium. |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/FR-3068257-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2023067273-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2019002788-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2713010-C1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/US-11479833-B2
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/FR-3063499-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/FR-3128460-A1 |
| priorityDate |
2015-07-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |