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1. WO1997025721 - RECOVERY OF ACTINIDES

Publication Number WO/1997/025721
Publication Date 17.07.1997
International Application No. PCT/GB1997/000062
International Filing Date 10.01.1997
Chapter 2 Demand Filed 26.07.1997
IPC
C01G 56/00 2006.01
CCHEMISTRY; METALLURGY
01INORGANIC CHEMISTRY
GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F94
56Compounds of transuranic elements
G21C 19/46 2006.01
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
19Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
42Reprocessing of irradiated fuel
44of irradiated solid fuel
46Aqueous processes
G21F 9/10 2006.01
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
9Treating radioactively contaminated material; Decontamination arrangements therefor
04Treating liquids
06Processing
10by flocculation
CPC
C01G 56/00
CCHEMISTRY; METALLURGY
01INORGANIC CHEMISTRY
GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
56Compounds of transuranic elements
G21C 19/46
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
19Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
42Reprocessing of irradiated fuel
44of irradiated solid fuel
46Aqueous processes ; , e.g. by using organic extraction means, including the regeneration of these means
G21F 9/10
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
9Treating radioactively contaminated material; Decontamination arrangements therefor
04Treating liquids
06Processing
10by flocculation
Y02E 30/30
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
30Energy generation of nuclear origin
30Nuclear fission reactors
Y02W 30/50
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
30Technologies for solid waste management
50Reuse, recycling or recovery technologies
Applicants
  • BRITISH NUCLEAR FUELS PLC [GB]/[GB] (AllExceptUS)
  • TAYLOR, Robin, John [GB]/[GB] (UsOnly)
  • DUNLOP, Alister, Andrew [GB]/[GB] (UsOnly)
  • JEAPES, Andrew, Philip [GB]/[GB] (UsOnly)
  • DENNISS, Ian, Stewart [GB]/[GB] (UsOnly)
  • PARKES, Peter [GB]/[GB] (UsOnly)
  • HOBBS, Jeffrey, William [GB]/[GB] (UsOnly)
  • SILVERWOOD, Paul, Richard [GB]/[GB] (UsOnly)
  • LIVENS, Francis, Robin [GB]/[GB] (UsOnly)
  • COLLISON, David [GB]/[GB] (UsOnly)
Inventors
  • TAYLOR, Robin, John
  • DUNLOP, Alister, Andrew
  • JEAPES, Andrew, Philip
  • DENNISS, Ian, Stewart
  • PARKES, Peter
  • HOBBS, Jeffrey, William
  • SILVERWOOD, Paul, Richard
  • LIVENS, Francis, Robin
  • COLLISON, David
Agents
  • HARRISON, Michael, Robert
Priority Data
9600286.010.01.1996GB
Publication Language English (EN)
Filing Language English (EN)
Designated States
Title
(EN) RECOVERY OF ACTINIDES
(FR) RETRAITEMENT D'ACTINIDES
Abstract
(EN)
A process for the separation of uranium and/or plutonium from a radioactive waste liquid comprising contacting the waste liquid with a carboxylic acid with precipitates from the waste liquid a complex formed between the uranium and/or plutonium and the carboxylic acid. The complex is then separated from the waste liquid.
(FR)
La présente invention concerne un procédé permettant de récupérer l'uranium et/ou le plutonium contenu dans un rejet liquide radioactif. Ce procédé consiste à mettre le rejet liquide en présence d'un acide carboxylique, ce qui produit alors dans le rejet liquide un précipité, à savoir un complexe se formant entre l'acide carboxylique et l'uranium et/ou le plutonium. Le procédé consiste alors à extraire le complexe contenu dans le rejet liquide.
Also published as
Latest bibliographic data on file with the International Bureau