http://rdf.ncbi.nlm.nih.gov/pubchem/patent/FR-2947663-B1
Outgoing Links
| 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/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/C01G56-001 |
| classificationIPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46 |
| filingDate | 2009-07-02-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| grantDate | 2011-07-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor | http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_e8b67a5ceb0d51f8fade661f3ae195cb http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_fe56d622b3f9ed20ecc4f3fa708356b1 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_88af1adad540663cd9aaacd22c556ce0 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_b003d7c48ae51ebedb21c9d798ba5e34 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_cf65870328b2da4fcf66a70c86d05ccc http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_85c9f2ca27aa1d0cdeee0939632cddd3 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_baffd65e76e0542457f794d03830f88d |
| publicationDate | 2011-07-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | FR-2947663-B1 |
| titleOfInvention | IMPROVED PROCESS FOR TREATING US NUCLEAR FUELS |
| abstract | The invention relates to a method of treating spent nuclear fuel, which comprises (a) decontaminating uranium, plutonium and neptunium present in an aqueous nitric phase, resulting from the dissolution of this nuclear fuel in HNO , with respect to actinides (III) and most of the fission products also present in this phase, this decontamination comprising at least the co-extraction of uranium, plutonium and neptunium in a solvent phase; (b) the partition of the uranium, plutonium and neptunium present in the solvent phase into a first aqueous phase containing either plutonium without U or Np, or a Pu + U mixture without Np, or a Pu + U + mixture Np, and a second aqueous phase containing either a U + Np mixture without Pu, or uranium without Pu or Np; (c) storing the first aqueous phase; (d) the purification of the plutonium or of the Pu + U mixture or of the Pu + U + Np mixture present in the first aqueous phase with respect to the fission products still present in this phase, this purification comprising at least one addition of uranium to obtain, at the end of this purification, an aqueous solution containing a Pu + U or Pu + U + Np mixture; and (e) co-converting the Pu + U mixture or the Pu + U + Np mixture thus obtained into a mixed oxide. |
| priorityDate | 2009-07-02-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 28.