Predicate |
Object |
assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_66e14891ed87b705b60e44596c647cfd |
classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B2235-3224 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B2235-3229 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B2235-3227 |
classificationCPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B35-447 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G21F9-162 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B35-50 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B35-645 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/C04B35-62204 |
classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C04B35-645 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C04B35-447 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G21F9-16 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C04B35-50 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/C04B35-622 |
filingDate |
2021-04-28-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_b4438fdbefe10ce29cab9be1e13e8020 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_1c20edaa4099672d8edb6aca3fad8528 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_040f81c9b452115c407b7a40387f5b6c http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_8e9dc753b4110563d92d4c8777fc0ff4 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_98a2cbeb4d9c563e0b3dd5875ba91032 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_ca273a183a997f9b906ea005234f9323 http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_d70cce784fb3668df1c8dea65cf3d2ad |
publicationDate |
2021-07-16-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
publicationNumber |
CN-113121220-A |
titleOfInvention |
Method for treating radioactive waste liquid by phosphate minerals |
abstract |
The invention discloses a method for treating radioactive waste liquid by phosphate minerals, which is characterized by comprising the following steps: trivalent lanthanides to mimic trivalent actinides, Th 4+ Simulating tetravalent actinides with LaCl 3 ·7H 2 O、CeCl 3 ·7H 2 O、PrCl 3 ·6H 2 O、NdCl 3 ·6H 2 O、SmCl 3 ·6H 2 O、EuCl 3 ·6H 2 O、GdCl 3 ·6H 2 O、NH 4 H 2 PO 4 、Th(NO 3 ) 4 ·4H 2 O、CaCl 2 、SrCl 2 ·6H 2 O as raw material, using CePO 4 ·0.667H 2 O-cerite precipitate enriched simulation actinide nuclide, and solid phase sintering is adopted to prepare M y Th y Ce 1‑x‑ 2y Ln x PO 4 The method can realize the high-efficiency volume reduction of the high-level radioactive waste liquid and the safe lattice solidification treatment of the actinide nuclide, so that the high-level radioactive waste liquid is safely treated. |
isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113912391-B http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113912391-A http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-116655355-B http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-116655355-A |
priorityDate |
2021-04-28-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
type |
http://data.epo.org/linked-data/def/patent/Publication |