GB201615592D0 - Simple reprocessing of nuclear fuel waste to produce reactor fuel - Google Patents
Simple reprocessing of nuclear fuel waste to produce reactor fuelInfo
- Publication number
- GB201615592D0 GB201615592D0 GBGB1615592.1A GB201615592A GB201615592D0 GB 201615592 D0 GB201615592 D0 GB 201615592D0 GB 201615592 A GB201615592 A GB 201615592A GB 201615592 D0 GB201615592 D0 GB 201615592D0
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- waste
- produce reactor
- simple reprocessing
- 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.)
- Withdrawn
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
-
- 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
- G21C19/50—Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/44—Fluid or fluent reactor fuel
- G21C3/54—Fused salt, oxide or hydroxide compositions
-
- 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)
- Electrolytic Production Of Metals (AREA)
Priority Applications (7)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1615592.1A GB2554068A (en) | 2016-09-14 | 2016-09-14 | Simple reprocessing of nuclear fuel waste to produce reactor fuel |
US16/085,568 US10622112B2 (en) | 2016-03-16 | 2017-03-14 | Conversion of spent uranium oxide fuel into molten salt reactor fuel |
GB1816421.0A GB2563792B8 (en) | 2016-03-16 | 2017-03-14 | Conversion of spent uranium oxide fuel into molten salt reactor fuel |
PCT/GB2017/050684 WO2017158335A1 (en) | 2016-03-16 | 2017-03-14 | Conversion of spent uranium oxide fuel into molten salt reactor fuel |
CN201780029654.9A CN109196596A (en) | 2016-03-16 | 2017-03-14 | Fusedsalt reactor fuel is converted by discarded uranium oxide fuel |
JP2018548717A JP6839719B2 (en) | 2016-03-16 | 2017-03-14 | Conversion of used uranium oxide fuel to molten salt reactor fuel |
CA3017462A CA3017462A1 (en) | 2016-03-16 | 2017-03-14 | Conversion of spent uranium oxide fuel into molten salt reactor fuel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1615592.1A GB2554068A (en) | 2016-09-14 | 2016-09-14 | Simple reprocessing of nuclear fuel waste to produce reactor fuel |
Publications (2)
Publication Number | Publication Date |
---|---|
GB201615592D0 true GB201615592D0 (en) | 2016-10-26 |
GB2554068A GB2554068A (en) | 2018-03-28 |
Family
ID=57234727
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1615592.1A Withdrawn GB2554068A (en) | 2016-03-16 | 2016-09-14 | Simple reprocessing of nuclear fuel waste to produce reactor fuel |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB2554068A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113795894A (en) * | 2020-10-14 | 2021-12-14 | 中广核研究院有限公司 | Spent fuel dry post-treatment method based on plasma |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2570700A (en) * | 2018-02-03 | 2019-08-07 | Richard Scott Ian | Continuous processing of spent nuclear fuel |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4814046A (en) * | 1988-07-12 | 1989-03-21 | The United States Of America As Represented By The United States Department Of Energy | Process to separate transuranic elements from nuclear waste |
US5141723A (en) * | 1991-10-03 | 1992-08-25 | The United States Of America As Represented By The United States Department Of Energy | Uranium chloride extraction of transuranium elements from LWR fuel |
JPH07333389A (en) * | 1994-06-07 | 1995-12-22 | Toshiba Corp | Reprocessing device for spent nuclear fuel |
JPH11218597A (en) * | 1998-02-03 | 1999-08-10 | Hitachi Ltd | Method for reprocessing spent fuel |
-
2016
- 2016-09-14 GB GB1615592.1A patent/GB2554068A/en not_active Withdrawn
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113795894A (en) * | 2020-10-14 | 2021-12-14 | 中广核研究院有限公司 | Spent fuel dry post-treatment method based on plasma |
Also Published As
Publication number | Publication date |
---|---|
GB2554068A (en) | 2018-03-28 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |