GB1043543A - Process for removing carbon from mixtures comprising carbon and radioactive material - Google Patents
Process for removing carbon from mixtures comprising carbon and radioactive materialInfo
- Publication number
- GB1043543A GB1043543A GB1258963A GB1258963A GB1043543A GB 1043543 A GB1043543 A GB 1043543A GB 1258963 A GB1258963 A GB 1258963A GB 1258963 A GB1258963 A GB 1258963A GB 1043543 A GB1043543 A GB 1043543A
- Authority
- GB
- United Kingdom
- Prior art keywords
- removes
- oxygen
- carbon
- volatile fission
- nuclear fuel
- 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
-
- 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
1,043,543. Processing spent nuclear fuel. MINNESOTA MINING & MANUFACTURING CO. March 29, 1963, No. 12589/63. Heading G6R. Radio-active and fissionable products are recovered from a mixture of these materials with carbon, e.g. a graphite clad spent nuclear fuel element, by a process in which the carbon is oxidized by heating the mixture in an atmosphere consisting of an inert gas and less than 7% by volume of oxygen. The nuclear fuel, e.g. uranium, remains behind, together with the non-volatile fission products, as the oxide and the volatile fission product oxides pass on together with CO2 and are trapped downstream of the furnace. The preferred atmosphere contains at least 3% by volume of oxygen at no more than 5% and the preferred heating temperature is 1550-1650‹ F. The inert portion of the atmosphere is preferably from Group O of the Periodic Table having an atomic weight of less than 200, e.g. He. The uranium is extracted from the residual oxide by the established nitric acid-T.B.P. process. The exhaust gases from the furnace contain CO2, some CO, inert gas, e.g. He, some oxygen and the volatile fission products. A nickel catalyst converts Co to Co2, a cold trap removes the most volatile fission products, pyrogallol removes oxygen, a hot copper coil removes iodine, tellurium and ruthenium, and purified lime water removes Co2. A further cold trap removes Xe and Kr, leaving He for possible re-use.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1258963A GB1043543A (en) | 1963-03-29 | 1963-03-29 | Process for removing carbon from mixtures comprising carbon and radioactive material |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1258963A GB1043543A (en) | 1963-03-29 | 1963-03-29 | Process for removing carbon from mixtures comprising carbon and radioactive material |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1043543A true GB1043543A (en) | 1966-09-21 |
Family
ID=10007433
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1258963A Expired GB1043543A (en) | 1963-03-29 | 1963-03-29 | Process for removing carbon from mixtures comprising carbon and radioactive material |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1043543A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3846969A (en) * | 1972-04-13 | 1974-11-12 | Du Pont | False-twist texturing yarn of polyester filaments having multilobal cross sections |
USRE29363E (en) | 1973-08-30 | 1977-08-23 | E. I. Du Pont De Nemours And Company | False-twist texturing yarn of polyester filaments having multilobal cross sections |
-
1963
- 1963-03-29 GB GB1258963A patent/GB1043543A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3846969A (en) * | 1972-04-13 | 1974-11-12 | Du Pont | False-twist texturing yarn of polyester filaments having multilobal cross sections |
USRE29363E (en) | 1973-08-30 | 1977-08-23 | E. I. Du Pont De Nemours And Company | False-twist texturing yarn of polyester filaments having multilobal cross sections |
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