GB834531A - Improvements in or relating to the recovery of plutonium from organic solvents - Google Patents
Improvements in or relating to the recovery of plutonium from organic solventsInfo
- Publication number
- GB834531A GB834531A GB35916/54A GB3591654A GB834531A GB 834531 A GB834531 A GB 834531A GB 35916/54 A GB35916/54 A GB 35916/54A GB 3591654 A GB3591654 A GB 3591654A GB 834531 A GB834531 A GB 834531A
- Authority
- GB
- United Kingdom
- Prior art keywords
- plutonium
- solution
- recovery
- aqueous
- recovered
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G56/00—Compounds of transuranic elements
- C01G56/001—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G56/00—Compounds of transuranic elements
- C01G56/004—Compounds of plutonium
-
- C—CHEMISTRY; METALLURGY
- C07—ORGANIC CHEMISTRY
- C07C—ACYCLIC OR CARBOCYCLIC COMPOUNDS
- C07C51/00—Preparation of carboxylic acids or their salts, halides or anhydrides
- C07C51/41—Preparation of salts of carboxylic acids
- C07C51/412—Preparation of salts of carboxylic acids by conversion of the acids, their salts, esters or anhydrides with the same carboxylic acid part
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
- C22B3/20—Treatment or purification of solutions, e.g. obtained by leaching
- C22B3/26—Treatment or purification of solutions, e.g. obtained by leaching by liquid-liquid extraction using organic compounds
- C22B3/32—Carboxylic acids
- C22B3/322—Oxalic acids
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Engineering & Computer Science (AREA)
- Inorganic Chemistry (AREA)
- Manufacturing & Machinery (AREA)
- Geology (AREA)
- Life Sciences & Earth Sciences (AREA)
- Geochemistry & Mineralogy (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- Oil, Petroleum & Natural Gas (AREA)
- Extraction Or Liquid Replacement (AREA)
Abstract
834,531. Recovery of plutonium. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. March 6, 1956 [Dec. 11, 1954], No. 35916/54. Class 39(4). Plutonium is recovered from a solution of plutonium nitrate in an organic solvent by mixing the solution with aqueous oxalic acid solution so as to precipitate plutonium oxalate. The precipitate collects in the aqueous phase and may be removed by filtration, any plutonium remaining in solution being recovered by oxidation with nitric acid and extraction with the organic solvent. The presence of nitric acid in the aqueous phase reduces the solubility of plutonium oxalate. The solution treated may be the tributyl phosphate extract of an aqueous aluminium nitrate solution of calcium fluoride slag resulting from the reduction of plutonium tetrafluoride by calcium metal.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB35916/54A GB834531A (en) | 1954-12-11 | 1954-12-11 | Improvements in or relating to the recovery of plutonium from organic solvents |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB35916/54A GB834531A (en) | 1954-12-11 | 1954-12-11 | Improvements in or relating to the recovery of plutonium from organic solvents |
Publications (1)
Publication Number | Publication Date |
---|---|
GB834531A true GB834531A (en) | 1960-05-11 |
Family
ID=10382973
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB35916/54A Expired GB834531A (en) | 1954-12-11 | 1954-12-11 | Improvements in or relating to the recovery of plutonium from organic solvents |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB834531A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1223353B (en) * | 1961-08-18 | 1966-08-25 | Atomic Energy Authority Uk | Process for the production of a mixture of uranium and plutonium oxides |
US3328133A (en) * | 1964-02-10 | 1967-06-27 | Japan Atomic Energy Res Inst | Method for direct recovery of plutonium from irradiated nuclear fuel |
GB2118759A (en) * | 1982-03-15 | 1983-11-02 | Euratom | Process for the recovery of plutonium from aqueous nitric solutions |
EP4332991A1 (en) * | 2022-09-02 | 2024-03-06 | Commissariat à l'énergie atomique et aux énergies alternatives | Process for the removal of uranium (vi) and an actinide (iv) from an organic solution by oxalic precipitation |
-
1954
- 1954-12-11 GB GB35916/54A patent/GB834531A/en not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1223353B (en) * | 1961-08-18 | 1966-08-25 | Atomic Energy Authority Uk | Process for the production of a mixture of uranium and plutonium oxides |
US3328133A (en) * | 1964-02-10 | 1967-06-27 | Japan Atomic Energy Res Inst | Method for direct recovery of plutonium from irradiated nuclear fuel |
GB2118759A (en) * | 1982-03-15 | 1983-11-02 | Euratom | Process for the recovery of plutonium from aqueous nitric solutions |
EP4332991A1 (en) * | 2022-09-02 | 2024-03-06 | Commissariat à l'énergie atomique et aux énergies alternatives | Process for the removal of uranium (vi) and an actinide (iv) from an organic solution by oxalic precipitation |
FR3139408A1 (en) | 2022-09-02 | 2024-03-08 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | PROCESS FOR DEEXTRACTION OF URANIUM(VI) AND AN ACTINIDE(IV) FROM AN ORGANIC SOLUTION BY OXALIC PRECIPITATION |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB1206776A (en) | Irradiated fuel reprocessing | |
FR2413762A1 (en) | PROCESS FOR RECOVERING ACTINIDES FROM RESIDUE SOLUTIONS RESULTING FROM THE FUEL RECYCLING TREATMENT | |
Sato | The extraction of uranyl nitrate from nitric acid solutions by tributyl phosphate | |
ES280459A1 (en) | A procedure for the extraction of metals from the aqueous solutions of your salts (Machine-translation by Google Translate, not legally binding) | |
GB1474529A (en) | ||
GB834529A (en) | Separation of plutonium from neutron-irradiated uranium | |
GB1528415A (en) | Actinide recovery by solvent extraction | |
GB834531A (en) | Improvements in or relating to the recovery of plutonium from organic solvents | |
GB835212A (en) | Concentration of plutonium | |
GB1247248A (en) | A method of recovering plutonium and uranium from fission products by liquid-liquid extraction | |
GB1452115A (en) | Method of selective stripping of plutonium for organic solvents loaded with plutonium | |
GB1130044A (en) | Method for removing lanthanides and trivalent actinides from aqueous nitrate solutions | |
ES306340A1 (en) | Method of separation of uranium from plutonium | |
GB1400367A (en) | Method for removing alkyl iodides from air by mercuric nitrate solution | |
GB1330535A (en) | Processing of irradiated nuclear reactor fuel | |
GB865699A (en) | Improvements in or relating to the recovery of plutonium | |
GB816628A (en) | A method of extracting uranium compounds from their solutions | |
ES309190A1 (en) | Process of separation of uranium and thorium starting from a solution containing these two elements | |
GB1304313A (en) | ||
GB1205169A (en) | Improvements in or relating to the processing or irradiated nuclear fuel | |
GB1324024A (en) | Method for the separation of neptunium and plutonium | |
GB945184A (en) | Improvements in or relating to plutonium extraction | |
GB1449122A (en) | Processing of uranium hexafluoride | |
GB822290A (en) | Improvements in or relating to a process for the treatment of nuclear fuel | |
GB1073115A (en) | Method for reprocessing mother liquors derived from the precipitation of plutonium by oxalic acid |