http://rdf.ncbi.nlm.nih.gov/pubchem/patent/GB-2045511-A
Outgoing Links
| Predicate | Object |
|---|---|
| assignee | http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_9e7dba2945ad4d0260010aa925dac98e |
| 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/G21F9-302 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C25B1-00 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-48 |
| classificationIPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C25B1-00 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-48 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21F9-30 |
| filingDate | 1979-03-09-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationDate | 1980-10-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | GB-2045511-A |
| titleOfInvention | Electrochemical reprocessing of nuclear fuels |
| abstract | A method for the reprocessing of irradiated nuclear fuel which is particularly suitable for use with fuel from fast reactors and has the advantage of being a dry process in which there is no danger of radiation damage to a solvent medium as in a wet process, comprises the steps of dissolving the fuel in a salt melt under such conditions that uranium and plutonium therein are converted to sulphate form. The plutonium sulphate may then be thermally decomposed to PuO2 and removed. The salt melt is then subjected to electrolysis conditions to achieve cathodic deposition of UO2 (and possibly PuO2). The salt melt can then be recycled or conditioned for final disposal. |
| priorityDate | 1979-03-09-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 52.