GB968037A - Improvements in or relating to the recovery of uranium values - Google Patents
Improvements in or relating to the recovery of uranium valuesInfo
- Publication number
- GB968037A GB968037A GB2989962A GB2989962A GB968037A GB 968037 A GB968037 A GB 968037A GB 2989962 A GB2989962 A GB 2989962A GB 2989962 A GB2989962 A GB 2989962A GB 968037 A GB968037 A GB 968037A
- Authority
- GB
- United Kingdom
- Prior art keywords
- nitric acid
- nuclear fuel
- uranium
- acid solution
- organic solvent
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements 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
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- 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
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
968, 037. Processing spent nuclear fuel. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. July 11, 1963 [Aug. 3, 1962], No. 29899/62. Heading G6R. In a cyclic process for recovering uranium values from irradiated nuclear fuel, an aqueous nitric acid solution containing uranium, plutonium, and fission products is contacted with an organic solvent which extracts uranium and plutonium, leaving fission products in the aqueous solution, the solvent is washed with a dilute aqueous nitric acid solution, and the wash solution is treated to remove organic solvent, fortified with nitric acid, and used to-dissolve neutron-irradiated uranium nuclear fuel. In an example, a 3N nitric acid solution is extracted with tributyl phosphate diluted with kerosene, the organic extract is stripped with 2. 4 N nitric acid, and this acid solution is washed with kerosene or steam-stripped to remove organic solvent, brought to 6 N strength, and fed to a continuously operating dissolver for nuclear fuel. Reference has been directed by the Comptroller to Specification 801, 743.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE635794D BE635794A (en) | 1962-08-03 | ||
GB2989962A GB968037A (en) | 1962-08-03 | 1962-08-03 | Improvements in or relating to the recovery of uranium values |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB2989962A GB968037A (en) | 1962-08-03 | 1962-08-03 | Improvements in or relating to the recovery of uranium values |
Publications (1)
Publication Number | Publication Date |
---|---|
GB968037A true GB968037A (en) | 1964-08-26 |
Family
ID=10299005
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2989962A Expired GB968037A (en) | 1962-08-03 | 1962-08-03 | Improvements in or relating to the recovery of uranium values |
Country Status (2)
Country | Link |
---|---|
BE (1) | BE635794A (en) |
GB (1) | GB968037A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3523765A (en) * | 1966-03-08 | 1970-08-11 | Commissariat Energie Atomique | Multistage process for extracting u and pu with solvent comprising tributylphosphate |
FR2455565A1 (en) * | 1979-04-30 | 1980-11-28 | Atomic Energy Authority Uk | PROCESS FOR ACCELERATING THE DISSOLUTION AND INCREASING THE SOLUBILITY IN NITRIC ACID OF PLUTONIUM DIOXIDE AND MIXED URANIUM / PLUTONIUM OXIDES AND THEIR RESIDUES |
-
0
- BE BE635794D patent/BE635794A/xx unknown
-
1962
- 1962-08-03 GB GB2989962A patent/GB968037A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3523765A (en) * | 1966-03-08 | 1970-08-11 | Commissariat Energie Atomique | Multistage process for extracting u and pu with solvent comprising tributylphosphate |
FR2455565A1 (en) * | 1979-04-30 | 1980-11-28 | Atomic Energy Authority Uk | PROCESS FOR ACCELERATING THE DISSOLUTION AND INCREASING THE SOLUBILITY IN NITRIC ACID OF PLUTONIUM DIOXIDE AND MIXED URANIUM / PLUTONIUM OXIDES AND THEIR RESIDUES |
Also Published As
Publication number | Publication date |
---|---|
BE635794A (en) | 1900-01-01 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB1206776A (en) | Irradiated fuel reprocessing | |
GB1528415A (en) | Actinide recovery by solvent extraction | |
GB1240766A (en) | Irradiated nuclear fuel recovery process | |
US4229421A (en) | Purification of plutonium | |
GB1247248A (en) | A method of recovering plutonium and uranium from fission products by liquid-liquid extraction | |
GB850957A (en) | A method of preparing fluoride-free uranium dioxide | |
GB1113237A (en) | Improvements in processes for simultaneously purifying and concentrating plutonium solutions | |
GB968037A (en) | Improvements in or relating to the recovery of uranium values | |
GB1306408A (en) | Reprocessing method for fuel and or breeder elements of nuclear reactors | |
GB1452115A (en) | Method of selective stripping of plutonium for organic solvents loaded with plutonium | |
GB1434501A (en) | Removal of tritium from irradiated material | |
GB1330535A (en) | Processing of irradiated nuclear reactor fuel | |
GB1047232A (en) | ||
GB1068969A (en) | Method of separation of uranium from plutonium | |
GB1260096A (en) | Organic phase reduction of uranium | |
GB1219146A (en) | Recovery of plutonium and uranium from reactor fuel elements | |
GB983380A (en) | A method of separating plutonium and uranium together from aqueous solution | |
GB1465241A (en) | Method for the extraction properties of a tributyl phosphate solution | |
GB1205169A (en) | Improvements in or relating to the processing or irradiated nuclear fuel | |
GB1304313A (en) | ||
GB1324024A (en) | Method for the separation of neptunium and plutonium | |
GB801742A (en) | Solvent extraction of neptunium | |
GB1207288A (en) | Process for the liquid-liquid extraction of uranium and plutonium | |
GB816628A (en) | A method of extracting uranium compounds from their solutions | |
GB822290A (en) | Improvements in or relating to a process for the treatment of nuclear fuel |