| Predicate |
Object |
| assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_1494780218a688608f3da318be874cc2 |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02W30-50 |
| classificationCPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B60-0213
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-42
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01F17-271
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B17-02
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G43-08
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-48 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-42 |
| filingDate |
2017-12-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| grantDate |
2020-09-22-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_b53242d3d44d1006e2ed7e1fe6e7ee5f
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_00e9087c2f2fdc41d06816298d0d1be3
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_5884288c3878efb1944104dea807d900
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_f84a10aaabf81ef2610d1bb271697bf8
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_fda3015e6f8541c9cac88da0fa3d8512
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_04454f9ed5456168adb81da1b84cb8fe
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_9d9763e0bdb6f9bf742e2e1248802a8d
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_ce426c826cdae775b957b704aad138b3 |
| publicationDate |
2020-09-22-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
RU-2732740-C1 |
| titleOfInvention |
Method of processing spent nuclear fuel nitride in salt melts |
| abstract |
FIELD: physics.SUBSTANCE: invention relates to nuclear power engineering, in particular to methods of processing spent nuclear fuel, and can be used in technology of processing spent nuclear fuel in closed nuclear fuel cycle circuit, extracted from fuel elements. Method of processing spent nitride nuclear fuel in salt melt includes its chlorination in melt of mixture of chlorides of alkali and/or alkali-earth metals containing cadmium dichloride. Chlorination is carried out in an apparatus for processing spent nitride nuclear fuel using an inert gas atmosphere. Apparatus has a heated zone in which there is a reactor with a chloride melt and a spent nitride nuclear fuel immersed therein, as well as a cold zone located under the reactor. During chlorination zone of apparatus with reactor is heated to temperature higher than 700 °C, nitride spent nuclear fuel is held in the melt until complete chlorination, wherein the apparatus cold zone is used for crystallisation of metal cadmium formed during chlorination.EFFECT: invention increases degree of conversion of spent nitride nuclear fuel in molten chloride to 100 %.1 cl, 3 dwg, 1 tbl |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2775563-C1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2783506-C1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2775564-C1 |
| priorityDate |
2017-12-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |