| Predicate |
Object |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02E30-30 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/B01D59-20
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21C19-42 |
| filingDate |
2002-12-17-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| grantDate |
2004-12-20-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_3236578deb7588b46f62fa33e8f973e5
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_097ccd546b8ae0f3714e92f2fa5bf98f
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_b4c493224cf70be18376ebba04cfa042
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_87663f977d1169a9b69a04539c73ec79
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_d9d665ff5808304cff9889727963aff0
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_cf0c9ee257a1cea87838851a87c149f7
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_dbfa251f6f557f36c9ec1cb7bde12b5b
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_4d2e55117f161e7d637c4e7906ea9cbd
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_fc1a75150abd5974daf210c98adbdb17
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_021704e44b91dcc2784f3fe7669d2545
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_d368e98cb8d23baa267eb555123fd2a7
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_ce1daffa4aad969b3d76298631370da1 |
| publicationDate |
2004-12-20-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
RU-2242812-C2 |
| titleOfInvention |
Isotope reduction of regenerated uranium |
| abstract |
FIELD: recycling nuclear power-generating materials. n n n SUBSTANCE: proposed method intended to enable reuse of uranium extracted from spent nuclear fuel in fuel cycle of light-water reactors by reducing its isotope involves increase of n n 235 n n U isotope content in regenerated uranium to 2.0 - 7.0 mass percent at the same time reducing relative concentration of isotopes n n 232 n n U, n n 234 n n U, and n n 236 n n U including direct enrichment of raw regenerated uranium hexafluoride in gas-centrifuge isotope-separating cascade; raw regenerated uranium is enriched by n n 235 n n U isotope to content of 21.0 - 90.0 mass percent in double cascade during extraction of reduced fuel material with n n 235 n n U isotope content not over 50.0%, preferably 2.0 - 36.0 mass percent, through waste flow of second ordinary cascade. Enrichment in first ordinary cascade is conducted up to n n 235 n n U content of 3.5 - 10.0 mass percent or 21.0 - 35.0 mass percent. This method provides for attaining desired enrichment of regenerated uranium by n n 235 n n U isotope at low content of noxious isotopes. n n n EFFECT: enhanced quality of regenerated uranium reduction due to absolute and relative control of noxious isotope content. n n n 7 cl, 3 dwg, 5 tbl |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2479489-C2
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2759155-C1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/RU-2497210-C1 |
| priorityDate |
2002-12-17-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |