GB1274357A - Improvements in or relating to the treatment of irradiated nuclear fuel elements - Google Patents
Improvements in or relating to the treatment of irradiated nuclear fuel elementsInfo
- Publication number
- GB1274357A GB1274357A GB5227/70A GB522770A GB1274357A GB 1274357 A GB1274357 A GB 1274357A GB 5227/70 A GB5227/70 A GB 5227/70A GB 522770 A GB522770 A GB 522770A GB 1274357 A GB1274357 A GB 1274357A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- sheath
- fuel element
- treatment
- 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
- G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
-
- 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
Abstract
1,274,357. Removing canning from nuclear fuel. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 19 April, 1971 [3 Feb., 1970], No. 5227/70. Heading G6R. The treatment of an irradiated fuel element comprising ceramic fuel, e.g. an oxide, enclosed in a metal sheath, e.g. of stainless steel, consists of rupturing the sheath by subjecting the fuel element to local induction heating generated by a radio-frequency magnetic field. The crack formed in the sheath by the induction heating coil is extended by moving the fuel element axially relatively to the coil. Rupture of the sheath permits the fuel material to be dissolved out without shearing the fuel element into short lengths.
Priority Applications (6)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB5227/70A GB1274357A (en) | 1970-02-03 | 1970-02-03 | Improvements in or relating to the treatment of irradiated nuclear fuel elements |
DE19712104350 DE2104350A1 (en) | 1970-02-03 | 1971-01-30 | Process for the preparation of irradiated core fuel elements |
BE762373A BE762373A (en) | 1970-02-03 | 1971-02-01 | TREATMENT OF NUCLEAR FUEL ELEMENTS |
FR7103485A FR2080952B1 (en) | 1970-02-03 | 1971-02-02 | |
CA104253A CA918246A (en) | 1970-02-03 | 1971-02-02 | Treatment of irradiated nuclear fuel elements |
US384837A US3929961A (en) | 1970-02-03 | 1973-08-02 | Treatment of irradiated nuclear fuel elements |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB5227/70A GB1274357A (en) | 1970-02-03 | 1970-02-03 | Improvements in or relating to the treatment of irradiated nuclear fuel elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1274357A true GB1274357A (en) | 1972-05-17 |
Family
ID=9792115
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB5227/70A Expired GB1274357A (en) | 1970-02-03 | 1970-02-03 | Improvements in or relating to the treatment of irradiated nuclear fuel elements |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE762373A (en) |
CA (1) | CA918246A (en) |
DE (1) | DE2104350A1 (en) |
FR (1) | FR2080952B1 (en) |
GB (1) | GB1274357A (en) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3228979A1 (en) * | 1982-08-03 | 1984-02-09 | Alkem Gmbh, 6450 Hanau | METHOD FOR REFURBISHING A CORE REACTOR FUEL |
FR2590068B1 (en) * | 1985-11-08 | 1987-12-11 | Novatome | METHOD FOR RECYCLING PREVIOUSLY IRRADIATED NUCLEAR FUEL PELLETS IN A FAST NEUTRAL NUCLEAR REACTOR |
FR2667533A1 (en) * | 1990-10-05 | 1992-04-10 | Commissariat Energie Atomique | Method for cutting up a metal tube by induction, and application to the separation of irradiated fuels from their metal sheath |
FR2710181B1 (en) * | 1993-09-13 | 1995-11-03 | Cogema | Method and device for induction cutting of elements of a nuclear installation. |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB1097597A (en) * | 1964-11-03 | 1968-01-03 | Atomic Energy Authority Uk | Improvements in or relating to the removal of sheaths from nuclear fuel elements |
DE1589815A1 (en) * | 1967-03-03 | 1970-05-14 | Kernforschung Gmbh Ges Fuer | Method and device for cutting through reactor fuel element shells, irradiation capsules or storage and transport containers by means of high frequency |
DE1589850A1 (en) * | 1967-03-03 | 1970-09-17 | Kernforschung Gmbh Ges Fuer | Method and device for separating reactor fuel element casings, irradiation capsules and the like. like |
-
1970
- 1970-02-03 GB GB5227/70A patent/GB1274357A/en not_active Expired
-
1971
- 1971-01-30 DE DE19712104350 patent/DE2104350A1/en active Pending
- 1971-02-01 BE BE762373A patent/BE762373A/en unknown
- 1971-02-02 FR FR7103485A patent/FR2080952B1/fr not_active Expired
- 1971-02-02 CA CA104253A patent/CA918246A/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
CA918246A (en) | 1973-01-02 |
DE2104350A1 (en) | 1971-08-19 |
FR2080952B1 (en) | 1975-01-17 |
BE762373A (en) | 1971-08-02 |
FR2080952A1 (en) | 1971-11-26 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |