GB833981A - Solvent-extraction of u from neutron-irradiated thorium - Google Patents
Solvent-extraction of u from neutron-irradiated thoriumInfo
- Publication number
- GB833981A GB833981A GB3012447A GB3012447A GB833981A GB 833981 A GB833981 A GB 833981A GB 3012447 A GB3012447 A GB 3012447A GB 3012447 A GB3012447 A GB 3012447A GB 833981 A GB833981 A GB 833981A
- Authority
- GB
- United Kingdom
- Prior art keywords
- solution
- thorium
- nitrate
- protoactinium
- uranium
- 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
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01F—COMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
- C01F15/00—Compounds of thorium
-
- 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
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Chemistry (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Extraction Or Liquid Replacement (AREA)
Abstract
833,981. Separation of uranium-233 and protoactinium. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Nov. 12, 1947 [Aug. 18, 1947], No. 30124/47. Class 39(4). Uranium-233 is separated from neutronirradiated thorium by forming an aqueous nitrate solution of the thorium of pH not less than 2 and contacting the solution with methyl iso-butyl ketone which extracts the uranyl nitrate. The thorium may be dissolved in concentrated nitric acid and the pH adjusted with ammonia, calcium hydroxide, or caustic alkali. Before extraction the solution may be saturated with calcium, ammonium, or zinc nitrate. Protoactinium is either extracted or not, according to the pH of the solution ; it may be recovered from the aqueous phase by making the solution about 1- normal in nitric acid and extracting again with methyl iso-butyl ketone.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CA833981X | 1947-08-18 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB833981A true GB833981A (en) | 1960-05-04 |
Family
ID=4172633
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3012447A Expired GB833981A (en) | 1947-08-18 | 1947-11-12 | Solvent-extraction of u from neutron-irradiated thorium |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB833981A (en) |
-
1947
- 1947-11-12 GB GB3012447A patent/GB833981A/en not_active Expired
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