GB981044A - Method of treating partly used nuclear fuels - Google Patents
Method of treating partly used nuclear fuelsInfo
- Publication number
- GB981044A GB981044A GB2212162A GB2212162A GB981044A GB 981044 A GB981044 A GB 981044A GB 2212162 A GB2212162 A GB 2212162A GB 2212162 A GB2212162 A GB 2212162A GB 981044 A GB981044 A GB 981044A
- Authority
- GB
- United Kingdom
- Prior art keywords
- hexafluorides
- converted
- partly used
- hydrofluoric acid
- used nuclear
- 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
- G21C19/48—Non-aqueous processes
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B32/00—Carbon; Compounds thereof
- C01B32/90—Carbides
- C01B32/914—Carbides of single elements
- C01B32/928—Carbides of actinides
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G1/00—Methods of preparing compounds of metals not covered by subclasses C01B, C01C, C01D, or C01F, in general
- C01G1/06—Halides
-
- 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
-
- 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
- C01G56/006—Halides
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G99/00—Subject matter not provided for in other groups of this subclass
- C01G99/006—Compounds containing, besides a metal not provided for elsewhere in this subclass, two or more other elements other than oxygen or hydrogen
-
- 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
-
- 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
-
- 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)
- Organic Chemistry (AREA)
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Inorganic Chemistry (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Geology (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Environmental & Geological Engineering (AREA)
- Carbon And Carbon Compounds (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Partly used nuclear fuel containing uranium or plutonium carbide is decontaminated from fission products by treatment with anhydrous or aqueous hydrofluoric acid to form UF4 and/or PuF4, or PuF3. The hydrofluoric acid may be in gaseous or liquid form and reaction may take place at a temperature up to 700 DEG C.; for example, the used fuel is diluted with alumina and treated as a fluidized bed with hydrogen fluoride vapour mixed with nitrogen, argon, or hydrogen. For complete decontamination, the product may be converted to the hexafluorides by the action of fluorine at 400 DEG C., and the hexafluorides purified by distillation. Alternatively the lower fluorides may be (a) reduced with calcium or magnesium metal in the presence of carbon or graphite to re-form the carbides; or (b) converted to oxides with steam at high temperature.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE482105 | 1961-06-22 | ||
BE605293 | 1961-06-22 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB981044A true GB981044A (en) | 1965-01-20 |
Family
ID=25655304
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2212162A Expired GB981044A (en) | 1961-06-22 | 1962-06-07 | Method of treating partly used nuclear fuels |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE605293A (en) |
DE (1) | DE1222486B (en) |
FR (1) | FR1333814A (en) |
GB (1) | GB981044A (en) |
LU (1) | LU41852A1 (en) |
NL (1) | NL278714A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5431891A (en) * | 1992-02-11 | 1995-07-11 | Companie Generale Des Matieres Nucleaires | Process for the recovery and purification of a metal alloy based on highly enriched uranium |
WO2001039209A2 (en) * | 1999-11-27 | 2001-05-31 | British Nuclear Fuels Plc | A method of separating uranium from irradiated nuclear fuel |
WO2008150188A1 (en) * | 2007-06-05 | 2008-12-11 | Nikolay Victorovich Stepanov | Method for processing spent nuclear fuel |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2705660A1 (en) * | 1992-02-11 | 1994-12-02 | Pechiney Uranium | Process for the recovery and purification of a metal alloy based on enriched uranium |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1004154B (en) * | 1955-12-09 | 1957-03-14 | Degussa | Process for the continuous production of uranium tetrafluoride from aqueous solution |
-
1961
- 1961-06-22 BE BE605293D patent/BE605293A/fr not_active Expired
-
1962
- 1962-05-15 DE DEE22881A patent/DE1222486B/en active Pending
- 1962-05-22 NL NL278714D patent/NL278714A/xx unknown
- 1962-06-05 FR FR899686A patent/FR1333814A/en not_active Expired
- 1962-06-07 GB GB2212162A patent/GB981044A/en not_active Expired
- 1962-06-08 LU LU41852D patent/LU41852A1/xx unknown
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5431891A (en) * | 1992-02-11 | 1995-07-11 | Companie Generale Des Matieres Nucleaires | Process for the recovery and purification of a metal alloy based on highly enriched uranium |
WO2001039209A2 (en) * | 1999-11-27 | 2001-05-31 | British Nuclear Fuels Plc | A method of separating uranium from irradiated nuclear fuel |
WO2001039209A3 (en) * | 1999-11-27 | 2002-03-21 | British Nuclear Fuels Plc | A method of separating uranium from irradiated nuclear fuel |
US6960326B1 (en) | 1999-11-27 | 2005-11-01 | British Nuclear Fuels Plc | Method of separating uranium from irradiated nuclear fuel |
WO2008150188A1 (en) * | 2007-06-05 | 2008-12-11 | Nikolay Victorovich Stepanov | Method for processing spent nuclear fuel |
Also Published As
Publication number | Publication date |
---|---|
DE1222486B (en) | 1966-08-11 |
NL278714A (en) | 1964-11-10 |
LU41852A1 (en) | 1962-08-08 |
FR1333814A (en) | 1963-08-02 |
BE605293A (en) | 1961-12-22 |
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