| Predicate |
Object |
| assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_dc97f70aef1120d77016fcac5764f032
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_33f8096f7c6f74ac787c777aaf01104a |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/B01D61-44 |
| classificationCPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B60-02
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G43-01
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B3-04
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G43-003
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C22B7-00 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C22B60-02
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C22B3-04
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C22B7-00 |
| filingDate |
2008-04-25-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_ba831a231ebea4f01ac4836f46ad7da6
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_a05f7a873d2d76634e59f3b6c81b8aa3
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_3434d862ce6bb260cb823d2f6258e0c8
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_0e6b15a2b2a773abd9bc5a485c7c7c1f
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_377612cb4c0d2d39e84891e011a2a1dd
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_d9b2bca1f4e308e02d5490f529d5c9c8
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_1626396e8517b29f510371e5728aa3af
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_eea16c8850abc57776a39d70dbb2f3b2
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_b1faf07794cfa0347b1884461ad83777 |
| publicationDate |
2009-10-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
KR-20090112862-A |
| titleOfInvention |
Separation Recovery Method of Uranium for Spent Fuel Using High Alkaline Carbonate Solution System and Its Apparatus |
| abstract |
The present invention relates to a method for recovering and recovering uranium from spent fuel using a high alkaline carbonate solution system. The object of the present invention is to select only uranium from spent fuel, while providing environmental protection to minimize nuclear proliferation resistance and waste generation. To separate and recover.n n n The present invention provides an oxidation power between the uranium oxide (UO 2 ) redox equilibrium voltage and the redox equilibrium voltage of plutonium oxide (PuO 2 ), neptunium oxide (NpO 2 ) and americium oxide (AmO 2 ). A uranium dissolution leaching step of dissolving only uranium (U) in the form of uranyl oxo carbonate complex ions by hydrogen peroxide (H 2 O 2 ), which is an oxidizing agent having a; Cesium-technetium precipitation step of precipitating and separating cesium (Cs) and technetium (Tc) by an organic precipitant; The uranium precipitate containing the uranium solution is adjusted to pH 2-4 by acid in the uranium precipitation tank to precipitate uranium in the form of UO 4 oxide and absorbs the carbon dioxide gas generated at the same time so that it can be recovered and recycled to the carbonate. Carbonate recovery step; And an acid-alkali recovery step for recovering the acid and alkali solution used in the uranium precipitation-carbonate recovery step while removing the impurity metal ions remaining in the solution depleted of uranium and carbonate. |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2017188538-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2018221811-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-112853095-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/KR-20200077280-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113215406-B
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113215406-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/KR-101648973-B1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/US-11289233-B2 |
| priorityDate |
2008-04-25-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |