http://rdf.ncbi.nlm.nih.gov/pubchem/patent/JP-H10282293-A
Outgoing Links
| Predicate | Object |
|---|---|
| assignee | http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_2d85e80d50edadc5f8e7fe1c05b34602 |
| 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/C25B1-00 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C01G56-00 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21C19-46 |
| classificationIPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-46 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C25B1-00 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21F9-10 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C01G56-00 |
| filingDate | 1997-04-04-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor | http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_4584b8d4006746db6c1b1d7fa50327ba http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_3e9700d736a0d251897302bbc3fe9c99 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_22314469e9515033af6ec6f4f9d7214d |
| publicationDate | 1998-10-23-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber | JP-H10282293-A |
| titleOfInvention | Recovery method of transuranium element from spent nuclear fuel |
| abstract | (57) [Summary] [PROBLEMS] To simplify the process of recovering transuranium element and reduce waste solvent and waste. SOLUTION: Spent nuclear fuel is dissolved in nitric acid (S10). 0), this solution is electrolytically oxidized, U, Np, Pu, Am are oxidized to VI valence using Ce as an oxidation catalyst, and further cooled. Crystallize the VI-valent nitrate and separate it from the mother liquor (S10 4). The mother liquor is heated and concentrated (S114). The mixed precipitate separated by crystallization is once dissolved in nitric acid (S10). 6) By cooling (S108), only uranyl nitrate is precipitated and crystallized and separated from a U, Np, Pu, Am mixed solution (S110). The uranyl nitrate is dissolved in nitric acid (S112), and the heated and concentrated mother liquor is added to the nitric acid solution to prepare a mixed solution. By subjecting the mixed solution to electrolytic oxidation, the remaining U, Np, Pu, and Am are recovered as VI. After being oxidized to a valence of four and cooled, U, Np, Pu and Am remaining after recovery are co-precipitated with uranyl nitrate, and separated by crystallization from a high-level radiation waste liquid (S118). |
| priorityDate | 1997-04-04-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Total number of triples: 42.