http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-H1164579-A
Outgoing Links
| Predicate | Object |
|---|---|
| assignee | http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_f80a7e640992b40ed091f53e7453e77e |
| 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 |
| filingDate | 1997-08-13-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor | http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_62d63da7aa5d944cf38f972cadf6e802 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_cc19f4066dac2d202ae5a7ec7cd7b77a http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_67ba0618e2b0156275c0696303aaff1f |
| publicationDate | 1999-03-05-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | JP-H1164579-A |
| titleOfInvention | Method for separating U and Pu present in an aqueous solution using a cyclic amide compound |
| abstract | (57) Abstract: The present invention relates to a method for extracting U (VI) ions and / or Pu (IV) ions present in an acidic aqueous solution using a cyclic amide. In particular, the U present in the spent nuclear fuel dissolved nitric acid solution obtained in the first stage of the spent nuclear fuel reprocessing is And to recover Pu. A cyclic amide compound having a peptide bond, ie, C 3 H 5 R 1 CONR 2 (butyrolactam: 5-membered ring), C 4 H 7 R 1 CONR 2 (valerolactam: 6-membered ring), C 5 A wide range of radionuclides, including a variety of radionuclides, are provided by extractants having monodentate functional groups such as H 9 R 1 CONR 2 (caprolactam: 7-membered ring) (where R 1 and R 2 are hydrogen atoms or organic chains). U or Pu is selectively separated from the aqueous solution. |
| priorityDate | 1997-08-13-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 40.