GB2352729B - Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same - Google Patents
Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the sameInfo
- Publication number
- GB2352729B GB2352729B GB0022698A GB0022698A GB2352729B GB 2352729 B GB2352729 B GB 2352729B GB 0022698 A GB0022698 A GB 0022698A GB 0022698 A GB0022698 A GB 0022698A GB 2352729 B GB2352729 B GB 2352729B
- Authority
- GB
- United Kingdom
- Prior art keywords
- carrying
- same
- nuclear fuel
- treating waste
- handling facility
- 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 - Fee Related
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
- 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
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Mechanical Engineering (AREA)
- Materials Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacturing & Machinery (AREA)
- Plasma & Fusion (AREA)
- Geology (AREA)
- Environmental & Geological Engineering (AREA)
- Electrolytic Production Of Metals (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP25809398A JP3868635B2 (en) | 1998-09-11 | 1998-09-11 | Method and apparatus for treating waste from nuclear fuel cycle facility |
GB9921320A GB2341396B (en) | 1998-09-11 | 1999-09-09 | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
Publications (3)
Publication Number | Publication Date |
---|---|
GB0022698D0 GB0022698D0 (en) | 2000-11-01 |
GB2352729A GB2352729A (en) | 2001-02-07 |
GB2352729B true GB2352729B (en) | 2002-04-24 |
Family
ID=26315917
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB0022698A Expired - Fee Related GB2352729B (en) | 1998-09-11 | 1999-09-09 | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB2352729B (en) |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3802871A (en) * | 1969-07-14 | 1974-04-09 | Kennecott Copper Corp | Refining of liquid copper |
EP0068469A2 (en) * | 1981-06-30 | 1983-01-05 | Amax Inc. | Refining copper-bearing material contaminated with nickel, antimony and/or tin |
US5336450A (en) * | 1992-12-31 | 1994-08-09 | The United States Of America As Represented By The United States Department Of Energy | Process to remove rare earth from IFR electrolyte |
JPH08122487A (en) * | 1994-10-20 | 1996-05-17 | Toshiba Corp | Reprocessing method of spent fuel and annihilationmethod of element having long half-life |
WO1996032729A1 (en) * | 1995-04-12 | 1996-10-17 | British Nuclear Fuels Plc | Method of processing oxide nuclear fuel |
JPH09152497A (en) * | 1995-11-30 | 1997-06-10 | Mitsubishi Materials Corp | Method and device for recovering spent nuclear fuel |
-
1999
- 1999-09-09 GB GB0022698A patent/GB2352729B/en not_active Expired - Fee Related
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3802871A (en) * | 1969-07-14 | 1974-04-09 | Kennecott Copper Corp | Refining of liquid copper |
EP0068469A2 (en) * | 1981-06-30 | 1983-01-05 | Amax Inc. | Refining copper-bearing material contaminated with nickel, antimony and/or tin |
US5336450A (en) * | 1992-12-31 | 1994-08-09 | The United States Of America As Represented By The United States Department Of Energy | Process to remove rare earth from IFR electrolyte |
JPH08122487A (en) * | 1994-10-20 | 1996-05-17 | Toshiba Corp | Reprocessing method of spent fuel and annihilationmethod of element having long half-life |
WO1996032729A1 (en) * | 1995-04-12 | 1996-10-17 | British Nuclear Fuels Plc | Method of processing oxide nuclear fuel |
JPH09152497A (en) * | 1995-11-30 | 1997-06-10 | Mitsubishi Materials Corp | Method and device for recovering spent nuclear fuel |
Non-Patent Citations (2)
Title |
---|
WPI Accession no 96-290875 & JP 08 122 487 A (1996-05-17) * |
WPI Accession no 97-360307 & JP 09 152 497 A (1997-06-10) * |
Also Published As
Publication number | Publication date |
---|---|
GB0022698D0 (en) | 2000-11-01 |
GB2352729A (en) | 2001-02-07 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
746 | Register noted 'licences of right' (sect. 46/1977) |
Effective date: 20070318 |
|
PCNP | Patent ceased through non-payment of renewal fee |
Effective date: 20170909 |