| Predicate |
Object |
| assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_80787665b837ed3eb503bbcd27c0043a |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02W30-50
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02E30-30 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/B01D11-04
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C01G56-00 |
| filingDate |
1994-10-17-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_bfc7fc86121742c0de3057f5712e5d90
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_4d1f5592ee53d7bebe38d6ad5a94c2bf
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_d3abaca3b11832a6a59f5d354709cc17 |
| publicationDate |
1996-05-07-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
JP-H08114696-A |
| titleOfInvention |
Neptunium recovery method |
| abstract |
(57) [Summary] [Structure] A co-decontamination process in which neptunium (VI) is continuously extracted together with uranium and plutonium while oxidizing neptunium with nitric acid in the dissolved solution of spent fuel; It consists of a partitioning step to separate plutonium from uranium and a purification step to purify each fraction. Neptunium is separated from short half-life fission producing nuclides by using tributyl phosphate as an extractant. [Effect] By controlling the valence of neptunium, It can be easily separated from fission product nuclides with a short half-life by solvent extraction, etc., and the management burden of high-level waste can be reduced. |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-112853128-B
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-112853128-A |
| priorityDate |
1994-10-17-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |