GB879041A - Improvements in or relating to the processing of nuclear reactor fuel elements - Google Patents
Improvements in or relating to the processing of nuclear reactor fuel elementsInfo
- Publication number
- GB879041A GB879041A GB151159A GB151159A GB879041A GB 879041 A GB879041 A GB 879041A GB 151159 A GB151159 A GB 151159A GB 151159 A GB151159 A GB 151159A GB 879041 A GB879041 A GB 879041A
- Authority
- GB
- United Kingdom
- Prior art keywords
- nuclear reactor
- solution
- reactor fuel
- relating
- processing
- 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
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 229910002651 NO3 Inorganic materials 0.000 abstract 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 abstract 2
- 229910052782 aluminium Inorganic materials 0.000 abstract 2
- 239000004411 aluminium Substances 0.000 abstract 2
- 150000001768 cations Chemical class 0.000 abstract 2
- -1 nitrate ions Chemical class 0.000 abstract 2
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 1
- 229910052770 Uranium Inorganic materials 0.000 abstract 1
- 239000002253 acid Substances 0.000 abstract 1
- 230000007812 deficiency Effects 0.000 abstract 1
- 239000000446 fuel Substances 0.000 abstract 1
- 238000000034 method Methods 0.000 abstract 1
- 229910017604 nitric acid Inorganic materials 0.000 abstract 1
- 239000003960 organic solvent Substances 0.000 abstract 1
- 238000011084 recovery Methods 0.000 abstract 1
- 229910052710 silicon Inorganic materials 0.000 abstract 1
- 239000010703 silicon Substances 0.000 abstract 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract 1
- 229910002007 uranyl nitrate Inorganic materials 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical group O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
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)
- Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)
Abstract
In a process for recovery of uranium from an irradiated nuclear reactor fuel element also containing aluminium and silicon, the fuel element is dissolved in a limited quantity of nitric acid to give a solution containing less than the stoichiometric equivalent of nitrate ions for the cations present and containing aluminium in the basic hydroxide form, and then uranyl nitrate is extracted from the solution with an organic solvent. Preferably the solution has an acid deficiency between 0.6 M and 2 M, i.e. lacks 0.6 to 2 moles of nitrate ions per litre for stoichiometric equivalence with the cations present. Examples are given.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB151159A GB879041A (en) | 1959-01-15 | 1959-01-15 | Improvements in or relating to the processing of nuclear reactor fuel elements |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB151159A GB879041A (en) | 1959-01-15 | 1959-01-15 | Improvements in or relating to the processing of nuclear reactor fuel elements |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB879041A true GB879041A (en) | 1961-10-04 |
Family
ID=9723241
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB151159A Expired GB879041A (en) | 1959-01-15 | 1959-01-15 | Improvements in or relating to the processing of nuclear reactor fuel elements |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB879041A (en) |
-
1959
- 1959-01-15 GB GB151159A patent/GB879041A/en not_active Expired
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