GB927735A - Preparation of uranium compounds - Google Patents
Preparation of uranium compoundsInfo
- Publication number
- GB927735A GB927735A GB2631761A GB2631761A GB927735A GB 927735 A GB927735 A GB 927735A GB 2631761 A GB2631761 A GB 2631761A GB 2631761 A GB2631761 A GB 2631761A GB 927735 A GB927735 A GB 927735A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- oxygen
- alloy
- gaseous
- molybdenum
- 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
- C01G43/00—Compounds of uranium
- C01G43/04—Halides of uranium
- C01G43/06—Fluorides
- C01G43/063—Hexafluoride (UF6)
- C01G43/066—Preparation
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
-
- 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
- C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
-
- 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
- G21C19/48—Non-aqueous processes
-
- 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)
- Organic Chemistry (AREA)
- Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Uranium compounds are prepared from an alloy containing uranium and molybdenum, e.g. an irradiated nuclear fuel, by p treating said alloy with a gaseous mixture containing hydrogen halide and molecular oxygen, the alloy, at least initially, being at a temperature from 100 DEG C. to 300 DEG C. in order to initiate the desired reaction. The preferred hydrogen halides are HCl and HF, and the molecular ratio of these halides to the oxygen in the gaseous mixtures used is from 0,5 to 10. The products are said to be oxides of uranium when the HCl-oxygen containing mixture is used, and uranium oxyfluoride and uranium fluoride when HF and oxygen are used. The product obtained which is substantially free of molybdenum can be fluoridized by treatment with fluorine or a halogen fluoride and then distilled to obtain substantially pure UF6, or alternatively, the uranium can be extracted from the oxide product by any suitable method. In addition to oxygen and hydrogen halide, the gas mixture may contain one or more gaseous diluents, e.g. up to 73% by vol. of nitrogen.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR834863A FR1272542A (en) | 1960-08-03 | 1960-08-03 | Process for recovering uranium, in particular in the form of uranium hexafluoride, from uranium-molybdenum alloys |
Publications (1)
Publication Number | Publication Date |
---|---|
GB927735A true GB927735A (en) | 1963-06-06 |
Family
ID=8736810
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2631761A Expired GB927735A (en) | 1960-08-03 | 1961-07-20 | Preparation of uranium compounds |
Country Status (8)
Country | Link |
---|---|
US (1) | US3208815A (en) |
BE (1) | BE606034A (en) |
CH (1) | CH435227A (en) |
DE (1) | DE1141628B (en) |
FR (1) | FR1272542A (en) |
GB (1) | GB927735A (en) |
LU (1) | LU40388A1 (en) |
NL (1) | NL267653A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2750127A1 (en) * | 1996-06-21 | 1997-12-26 | Us Energy | PURIFICATION OF URANIUM ALLOYS BY DIFFERENTIAL OXIDE SOLUBILITY AND PRODUCTION OF PURIFIED FUEL PRECURSORS |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2004967A1 (en) * | 1969-03-14 | 1970-09-24 | The Babcock & Wilcox Company, New York, N.Y. (V.St.A.) | Process for the recovery of components from nuclear fuel scrap |
JPS5233280B2 (en) * | 1974-02-07 | 1977-08-26 | ||
FR2687140B1 (en) * | 1992-02-11 | 1994-05-13 | Pechiney Uranium | METHOD FOR RECOVERING AND PURIFYING A HIGHLY ENRICHED URANIUM-BASED METAL ALLOY. |
FR2692880B1 (en) * | 1992-06-29 | 1994-09-02 | Pechiney Uranium | Process for the selective electro-fluorination of alloys or metallic mixtures based on uranium. |
EP2580763B1 (en) | 2010-06-09 | 2015-07-22 | General Atomics | Methods and apparatus for selective gaseous extraction of molybdenum-99 and other fission product radioisotopes |
US9567237B2 (en) | 2012-11-16 | 2017-02-14 | Honeywell International Inc. | Separation and recovery of molybdenum values from uranium process distillate |
RU2713745C1 (en) * | 2019-06-25 | 2020-02-07 | Федеральное государственное унитарное предприятие "Научно-исследовательский институт Научно-производственное объединение "ЛУЧ" (ФГУП "НИИ НПО "ЛУЧ") | Method of processing uranium-molybdenum composition |
Family Cites Families (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2582941A (en) * | 1944-10-12 | 1952-01-15 | Coleman D Wilder | Processes of producing uranium chlorides |
US2869982A (en) * | 1945-04-12 | 1959-01-20 | Harrison S Brown | Recovery of pu values by fluorination and fractionation |
US2865704A (en) * | 1947-01-08 | 1958-12-23 | Arthur H Jaffey | Method of separating uranium, plutonium, and fission products by bromination and distillation |
US2859096A (en) * | 1947-02-24 | 1958-11-04 | Fowler Robert Dudley | Process for production of uranium hexafluoride |
US2910344A (en) * | 1948-04-09 | 1959-10-27 | Norman R Davidson | Method of preparing uf |
US2887356A (en) * | 1955-09-21 | 1959-05-19 | Horizons Titanium Corp | Production of oxygen-free and anhydrous fused salt electrolyte from oxygen containing compounds of uranium |
US2907630A (en) * | 1958-02-06 | 1959-10-06 | Lawroski Stephen | Preparation of uranium hexafluoride |
NL276441A (en) * | 1961-03-30 | 1900-01-01 |
-
0
- NL NL267653D patent/NL267653A/xx unknown
-
1960
- 1960-08-03 FR FR834863A patent/FR1272542A/en not_active Expired
-
1961
- 1961-07-10 US US12290161 patent/US3208815A/en not_active Expired - Lifetime
- 1961-07-10 DE DEC24573A patent/DE1141628B/en active Pending
- 1961-07-11 LU LU40388D patent/LU40388A1/xx unknown
- 1961-07-12 BE BE606034A patent/BE606034A/en unknown
- 1961-07-14 CH CH829161A patent/CH435227A/en unknown
- 1961-07-20 GB GB2631761A patent/GB927735A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2750127A1 (en) * | 1996-06-21 | 1997-12-26 | Us Energy | PURIFICATION OF URANIUM ALLOYS BY DIFFERENTIAL OXIDE SOLUBILITY AND PRODUCTION OF PURIFIED FUEL PRECURSORS |
Also Published As
Publication number | Publication date |
---|---|
CH435227A (en) | 1967-05-15 |
FR1272542A (en) | 1961-09-29 |
BE606034A (en) | 1961-11-03 |
DE1141628B (en) | 1962-12-27 |
LU40388A1 (en) | 1961-09-11 |
US3208815A (en) | 1965-09-28 |
NL267653A (en) | 1900-01-01 |
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