http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CA-1126961-A
Outgoing Links
| Predicate | Object |
|---|---|
| assignee | http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_9e7dba2945ad4d0260010aa925dac98e |
| classificationIPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C22B60-02 |
| filingDate | 1979-03-12-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| grantDate | 1982-07-06-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor | http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_8174bdcc08e0e28fcc8c35791e50cc2a http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_aec35c7658601d6274abc11fa4dbc262 |
| publicationDate | 1982-07-06-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | CA-1126961-A |
| titleOfInvention | Pyroelectrochemical process for reprocessing irradiated nuclear fuels |
| abstract | ABSTRACT OF THE DISCLOSURE: The invention is concerned with a pyroelectrothemical method for the reprocessing of irradiated nuclear fuels, characte-rized in that it comprises the steps of dissolving the nuclear fuel, containing fission products, in a bath comprising molten alkali metal sulfates; thermally decomposing the plutonium sul-fate Pu(SO4)2, formed in said molten bath to plutonium oxide, PuO2; electrodepositing uranium oxide, on the cathode of an elec-trolytic cell provided in said molten bath; recycling the melted sulfates of said molten bath to the start of the process; and conditioning said fission products and the said melted sulfates. The process according to the invention is more particularly usa-ble for a final disposal of said melted salts and fission products. |
| priorityDate | 1979-03-12-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 40.