http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-H11118982-A
Outgoing Links
| Predicate | Object |
|---|---|
| assignee | http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_0950e9df7f0e1b73efee1bda859951ad |
| 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/C25C3-34 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-48 |
| classificationIPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-48 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C25C3-34 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-44 |
| filingDate | 1997-10-17-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor | http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_361e34d98fbae982ea6a59e2dfb2cd8c http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_2eff88cae668234254d90895bdf23414 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_723948f3ff50b08e8150d6b40faa410a http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_65285f24af12fde4825ba9e591be4f49 |
| publicationDate | 1999-04-30-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | JP-H11118982-A |
| titleOfInvention | How to treat spent reactor fuel |
| abstract | (57) [Summary] [PROBLEMS] To reduce the entrainment amount of metal nuclear fuel components to components of cladding tubes and the like that become waste, improve the recovery rate of metal nuclear fuel components, and reduce the amount of waste of cladding tubes and other components. Provided is a method for treating spent nuclear reactor fuel which can be reduced. A melting / separating step of a cladding tube or the like for melting an alloy cladding tube by first heating an object to be treated at a temperature not lower than the melting point of the alloy cladding tube and not higher than the melting point of the metal nuclear fuel material; The metal nuclear fuel material from which the alloy cladding tube or end plug has been removed in the process is immersed in a salt comprising a molten alkali metal chloride or an alkaline earth metal chloride or a mixture of both to dissolve the metal nuclear fuel material, Molten salt electric field process 5 for precipitating uranium, uranium and plutonium, or uranium, plutonium and transuranium elements, and removing the object to be treated from the salt and depositing chloride or alkaline earth metal adhering to the precipitated element at normal pressure Alternatively, there is provided an evaporative separation step 6 or 9 for evaporating and separating by heating under reduced pressure. |
| isCitedBy | http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2016136898-A1 http://rdf.ncbi.nlm.nih.gov/pubchem/patent/KR-101292912-B1 http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-4533514-B2 http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-2016090341-A http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-2002055196-A http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-2015230170-A http://rdf.ncbi.nlm.nih.gov/pubchem/patent/US-8889073-B2 |
| priorityDate | 1997-10-17-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 64.