http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-H10260292-A
Outgoing Links
| Predicate | Object |
|---|---|
| assignee | http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_435b20ff8b66a9a5de90cbd2255536a6 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/C01G43-00 |
| filingDate | 1997-03-19-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor | http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_19d20fb4feaec0d5016579b3fa011df4 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_02c000df74e69b1cb320aff23aa347c0 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_5d1124915a69443f427901760ad33750 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_43c10d18abf5bf758366479bb14076e2 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_7fa217700460434865f5192127f3b022 |
| publicationDate | 1998-09-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | JP-H10260292-A |
| titleOfInvention | Reprocessing of spent fuel |
| abstract | PROBLEM TO BE SOLVED: To provide a method for reprocessing spent fuel to produce MOX having a Pu / U ratio suitable for light water reactor or fast reactor fuel and uranium oxide of light water reactor fuel. . SOLUTION: A reprocessing method includes a step of shearing a spent fuel containing uranium U, plutonium Pu, and fission products (FP) and dissolving it in a nitric acid solution (1), using the relationship between the temperature of the nitric acid solution and the U concentration. (2) crystallizing and separating a part of uranium from the nitric acid solution to adjust the Pu / U ratio in the nitric acid solution, and contacting the nitric acid solution with an ion exchanger to obtain a Pu / U ratio of U; Step (5) for separating and decontaminating FP by adsorbing Pu Any Pu / U each obtained in the form of nitrate in (5) A step of heating the U and Pu in a ratio to convert them into oxides to obtain MOX (6), and a step of heating uranium separated in the form of nitrate in step (2) to obtain uranium oxide (3). It consists of. |
| priorityDate | 1997-03-19-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 40.