GB201604459D0 - Electrochemical reduction of spent nuclear fuel at high temperatures - Google Patents

Electrochemical reduction of spent nuclear fuel at high temperatures

Info

Publication number
GB201604459D0
GB201604459D0 GBGB1604459.6A GB201604459A GB201604459D0 GB 201604459 D0 GB201604459 D0 GB 201604459D0 GB 201604459 A GB201604459 A GB 201604459A GB 201604459 D0 GB201604459 D0 GB 201604459D0
Authority
GB
United Kingdom
Prior art keywords
high temperatures
nuclear fuel
electrochemical reduction
spent nuclear
spent
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Withdrawn
Application number
GBGB1604459.6A
Other versions
GB2548378A (en
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Priority to GB1604459.6A priority Critical patent/GB2548378A/en
Publication of GB201604459D0 publication Critical patent/GB201604459D0/en
Priority to CA3017462A priority patent/CA3017462A1/en
Priority to GB1816421.0A priority patent/GB2563792B8/en
Priority to PCT/GB2017/050684 priority patent/WO2017158335A1/en
Priority to US16/085,568 priority patent/US10622112B2/en
Priority to CN201780029654.9A priority patent/CN109196596A/en
Priority to JP2018548717A priority patent/JP6839719B2/en
Publication of GB2548378A publication Critical patent/GB2548378A/en
Withdrawn legal-status Critical Current

Links

Classifications

    • 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
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C3/00—Electrolytic production, recovery or refining of metals by electrolysis of melts
    • C25C3/34—Electrolytic production, recovery or refining of metals by electrolysis of melts of metals not provided for in groups C25C3/02 - C25C3/32
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25B—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES FOR THE PRODUCTION OF COMPOUNDS OR NON-METALS; APPARATUS THEREFOR
    • C25B1/00—Electrolytic production of inorganic compounds or non-metals
    • C25B1/01—Products
    • C25B1/02—Hydrogen or oxygen
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C3/00—Electrolytic production, recovery or refining of metals by electrolysis of melts
    • C25C3/36—Alloys obtained by cathodic reduction of all their ions
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C7/00—Constructional parts, or assemblies thereof, of cells; Servicing or operating of cells
    • C25C7/005—Constructional parts, or assemblies thereof, of cells; Servicing or operating of cells of cells for the electrolysis of melts
    • 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
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—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
GB1604459.6A 2016-03-16 2016-03-16 Electrochemical reduction of spent nuclear fuel at high temperatures Withdrawn GB2548378A (en)

Priority Applications (7)

Application Number Priority Date Filing Date Title
GB1604459.6A GB2548378A (en) 2016-03-16 2016-03-16 Electrochemical reduction of spent nuclear fuel at high temperatures
CA3017462A CA3017462A1 (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
US16/085,568 US10622112B2 (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

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB1604459.6A GB2548378A (en) 2016-03-16 2016-03-16 Electrochemical reduction of spent nuclear fuel at high temperatures

Publications (2)

Publication Number Publication Date
GB201604459D0 true GB201604459D0 (en) 2016-04-27
GB2548378A GB2548378A (en) 2017-09-20

Family

ID=55952390

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1604459.6A Withdrawn GB2548378A (en) 2016-03-16 2016-03-16 Electrochemical reduction of spent nuclear fuel at high temperatures

Country Status (1)

Country Link
GB (1) GB2548378A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113684504A (en) * 2021-07-27 2021-11-23 西安交通大学 Electrolytic refining waste molten salt treatment method for spent fuel dry-process post-treatment

Families Citing this family (1)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB862860A (en) * 1957-10-09 1961-03-15 Atomic Energy Commission Purification of thorium or uranium, or thorium-uranium alloys
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
JP2000284090A (en) * 1999-03-31 2000-10-13 Sumitomo Metal Mining Co Ltd Method for reprocessing spent nuclear fuel
KR101513652B1 (en) * 2013-11-04 2015-04-20 한국원자력연구원 Method of processing composite wastes

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113684504A (en) * 2021-07-27 2021-11-23 西安交通大学 Electrolytic refining waste molten salt treatment method for spent fuel dry-process post-treatment

Also Published As

Publication number Publication date
GB2548378A (en) 2017-09-20

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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)