GB1194624A - Oven for Processing Irradiated Nuclear Fuels - Google Patents
Oven for Processing Irradiated Nuclear FuelsInfo
- Publication number
- GB1194624A GB1194624A GB2342568A GB2342568A GB1194624A GB 1194624 A GB1194624 A GB 1194624A GB 2342568 A GB2342568 A GB 2342568A GB 2342568 A GB2342568 A GB 2342568A GB 1194624 A GB1194624 A GB 1194624A
- Authority
- GB
- United Kingdom
- Prior art keywords
- crucible
- ingot
- molten metal
- furnace
- 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
-
- 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
-
- 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
-
- 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
- G21C19/48—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
Abstract
1,194,624. Processing spent nuclear fuel. EUROPEAN ATOMIC ENERGY COMMUNITY. 16 May, 1968 [19 May, 1967], No. 23425/68. Heading G6R. [Also in Division F3-F4] Irradiated nuclear fuel elements are melted down in the graphite crucible of an electrically heated tilting furnace (see Division F3-F4), the molten metal produced is degassed in a vacuum or an inert atmosphere, a precipitation inducing metal is added to the molten metal and mixed with it by tilting of the crucible, and then precipitated fissile material such as uranium, is allowed to settle out of the mixture whilst the crucible is kept stationary and maintained at a controlled temperature. The material in the crucible is finally allowed to cool to form an ingot in which the fissile material is concentrated at the bottom end, which may be sawn off for further processing after removal of the ingot from the crucible. Preferably the furnace is located in a shielded cell close to a storage pool for the fuel elements.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE698675 | 1967-05-19 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1194624A true GB1194624A (en) | 1970-06-10 |
Family
ID=3850830
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2342568A Expired GB1194624A (en) | 1967-05-19 | 1968-05-16 | Oven for Processing Irradiated Nuclear Fuels |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE698675A (en) |
DE (1) | DE1758368A1 (en) |
FR (1) | FR1562712A (en) |
GB (1) | GB1194624A (en) |
LU (1) | LU56081A1 (en) |
NL (1) | NL6807015A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0100989A2 (en) * | 1982-08-12 | 1984-02-22 | Alkem Gmbh | Apparatus for treating granular substances, especially a powdery nuclear reactor combustible, and operating process for the apparatus |
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 |
---|---|---|---|---|
FR2642218B1 (en) * | 1989-01-24 | 1992-07-24 | Commissariat Energie Atomique | PRESSURE DISSOLUTION APPARATUS |
-
1967
- 1967-05-19 BE BE698675D patent/BE698675A/xx unknown
-
1968
- 1968-05-15 FR FR1562712D patent/FR1562712A/fr not_active Expired
- 1968-05-15 LU LU56081D patent/LU56081A1/xx unknown
- 1968-05-16 GB GB2342568A patent/GB1194624A/en not_active Expired
- 1968-05-17 NL NL6807015A patent/NL6807015A/xx unknown
- 1968-05-20 DE DE19681758368 patent/DE1758368A1/en active Pending
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0100989A2 (en) * | 1982-08-12 | 1984-02-22 | Alkem Gmbh | Apparatus for treating granular substances, especially a powdery nuclear reactor combustible, and operating process for the apparatus |
EP0100989A3 (en) * | 1982-08-12 | 1985-08-21 | Alkem Gmbh | Apparatus for treating granular substances, especially a powdery nuclear reactor combustible, and operating process for the apparatus |
WO2008150188A1 (en) * | 2007-06-05 | 2008-12-11 | Nikolay Victorovich Stepanov | Method for processing spent nuclear fuel |
Also Published As
Publication number | Publication date |
---|---|
LU56081A1 (en) | 1968-09-09 |
BE698675A (en) | 1967-11-20 |
FR1562712A (en) | 1969-04-04 |
DE1758368A1 (en) | 1971-01-07 |
NL6807015A (en) | 1968-11-20 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |