GB0909309D0 - Spent fuel reprocessing method - Google Patents

Spent fuel reprocessing method

Info

Publication number
GB0909309D0
GB0909309D0 GB0909309A GB0909309A GB0909309D0 GB 0909309 D0 GB0909309 D0 GB 0909309D0 GB 0909309 A GB0909309 A GB 0909309A GB 0909309 A GB0909309 A GB 0909309A GB 0909309 D0 GB0909309 D0 GB 0909309D0
Authority
GB
United Kingdom
Prior art keywords
spent fuel
fuel reprocessing
reprocessing method
spent
reprocessing
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.)
Granted
Application number
GB0909309A
Other versions
GB2461370B (en
GB2461370A (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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Publication of GB0909309D0 publication Critical patent/GB0909309D0/en
Publication of GB2461370A publication Critical patent/GB2461370A/en
Application granted granted Critical
Publication of GB2461370B publication Critical patent/GB2461370B/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C1/00—Electrolytic production, recovery or refining of metals by electrolysis of solutions
    • C25C1/22—Electrolytic production, recovery or refining of metals by electrolysis of solutions of metals not provided for in groups C25C1/02 - C25C1/20
    • 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
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • 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
    • 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
    • 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling
    • 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)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Electrochemistry (AREA)
  • Materials Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Electrolytic Production Of Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Electrolytic Production Of Non-Metals, Compounds, Apparatuses Therefor (AREA)
GB0909309A 2008-05-30 2009-05-29 Spent fuel reprocessing method Expired - Fee Related GB2461370B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2008143431A JP5193687B2 (en) 2008-05-30 2008-05-30 Spent fuel reprocessing method

Publications (3)

Publication Number Publication Date
GB0909309D0 true GB0909309D0 (en) 2009-07-15
GB2461370A GB2461370A (en) 2010-01-06
GB2461370B GB2461370B (en) 2010-10-20

Family

ID=40902333

Family Applications (1)

Application Number Title Priority Date Filing Date
GB0909309A Expired - Fee Related GB2461370B (en) 2008-05-30 2009-05-29 Spent fuel reprocessing method

Country Status (6)

Country Link
US (1) US20090294299A1 (en)
JP (1) JP5193687B2 (en)
CN (1) CN101593566B (en)
FR (1) FR2931989A1 (en)
GB (1) GB2461370B (en)
RU (1) RU2403634C1 (en)

Families Citing this family (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2960690B1 (en) * 2010-05-27 2012-06-29 Commissariat Energie Atomique PROCESS FOR PROCESSING NUCLEAR FUELS USING NO PLUTONIUM REDUCING EXTRACTION OPERATION
FR2971948B1 (en) 2011-02-28 2013-03-29 Commissariat Energie Atomique PROCESS FOR PRECIPITATION OF ONE OR MORE SOLUTES
JP5758209B2 (en) * 2011-06-14 2015-08-05 株式会社東芝 Spent fuel reprocessing method
CN102412002B (en) * 2011-09-06 2013-10-30 中国原子能科学研究院 N2O4Device for oxidation regulation of plutonium valence state
FR2980468B1 (en) * 2011-09-26 2014-01-24 Commissariat Energie Atomique PROCESS FOR THE PREPARATION OF AN OXYHALIDE AND / OR ACTINIDE OXIDE (S) AND / OR LANTHANIDE (S) FROM A MEDIUM COMPRISING AT LEAST ONE MELT SALT
JP5784476B2 (en) * 2011-12-09 2015-09-24 株式会社東芝 Uranium recovery method
JP5944237B2 (en) * 2012-06-15 2016-07-05 株式会社東芝 Method for recovering nuclear fuel material
FR2992330B1 (en) * 2012-06-26 2014-08-08 Commissariat Energie Atomique PROCESS FOR SEPARATING AT LEAST ONE FIRST E1 CHEMICAL ELEMENT OF AT LEAST ONE SECOND E2 CHEMICAL ELEMENT INVOLVING THE USE OF A MEDIUM COMPRISING A SPECIFIED MELT SALT
KR101316925B1 (en) * 2012-10-08 2013-10-18 한국수력원자력 주식회사 Treatment method of spent uranium catalyst
RU2561065C1 (en) * 2014-03-31 2015-08-20 Открытое акционерное общество "Радиевый институт имени В.Г. Хлопина" METHOD OF PRODUCING COMBINED SOLUTION OF U AND Pu
CN104008785B (en) * 2014-06-16 2016-08-17 中国工程物理研究院核物理与化学研究所 A kind of metal mold spentnuclear fuel after-treatment device
CN104143365B (en) * 2014-07-08 2017-02-01 中国核电工程有限公司 Neutron poison sandwich structure with openings in continuous dissolver
KR101918087B1 (en) * 2014-08-18 2018-11-13 드 노라 페르멜렉 가부시키가이샤 Method for treating tritium-water-containing raw water
CN104562089B (en) * 2014-10-17 2017-03-22 中国原子能科学研究院 Method for preparing initial molten salt system in molten salt electrolysis dry after-treatment process
GB2545934A (en) * 2016-01-02 2017-07-05 Richard Scott Ian Single stage reprocessing of spent nuclear fuel
CN108389641B (en) * 2017-12-28 2019-07-26 中国科学院近代物理研究所 A kind of preparation facilities and preparation method of nuclear fuel bead
CN109324070B (en) * 2018-08-08 2021-04-02 中国原子能科学研究院 Passive neutron analysis method for uranium plutonium content in waste cladding
JP7074615B2 (en) * 2018-08-27 2022-05-24 株式会社東芝 Neutron supply device and neutron supply method
CN109402413B (en) * 2018-10-30 2020-11-03 中国工程物理研究院核物理与化学研究所 Method for recovering palladium in fission product of spent fuel element
CN111188084B (en) * 2020-01-09 2021-04-02 中国原子能科学研究院 Replaceable integral electrode suitable for hot chamber application and electrode replacing device
WO2022077250A1 (en) * 2020-10-14 2022-04-21 中广核研究院有限公司 Dry aftertreatment method for spent fuel employing plasma
CN113684504B (en) * 2021-07-27 2022-12-09 西安交通大学 Electrolytic refining waste molten salt treatment method for spent fuel dry-process post-treatment
CN114752783B (en) * 2022-04-22 2023-10-03 厦门稀土材料研究所 High-efficiency Sr separation 2+ And Cs + Is a method of (2)
CN116665942B (en) * 2023-05-29 2024-01-23 西安交通大学 Spent fuel nuclide pre-separation method

Family Cites Families (21)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3276850A (en) * 1965-03-10 1966-10-04 Robert H Rainey Method of selectively reducing plutonium values
US2833800A (en) * 1947-12-19 1958-05-06 Donald F Mastick Process for purifying plutonium
US2990240A (en) * 1952-08-11 1961-06-27 Charles V Ellison Process for segregating uranium from plutonium and fission-product contamination
GB1096592A (en) * 1965-01-22 1967-12-29 Atomic Energy Authority Uk Electrolytic reduction for solutions containing nuclear fuel material
US4131527A (en) * 1977-03-30 1978-12-26 The United States Of America As Represented By The United States Department Of Energy Method for selectively reducing plutonium values by a photochemical process
US4162230A (en) * 1977-12-28 1979-07-24 The United States Of America As Represented By The United States Department Of Energy Method for the recovery of actinide elements from nuclear reactor waste
US4278559A (en) * 1978-02-16 1981-07-14 Electric Power Research Institute Method for processing spent nuclear reactor fuel
DE3345199A1 (en) * 1983-12-14 1985-06-27 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR REDUCTIVE PLUTONIUM RETURN EXTRACTION FROM AN ORGANIC REPROCESSING SOLUTION IN AN AQUEOUS, Nitric Acid Solution Using an Electrolysis Stream
CN1037914C (en) * 1993-03-04 1998-04-01 清华大学 Method for separating actinide elements from concentrated high-radioactive waste liquid
JP2726375B2 (en) * 1993-08-13 1998-03-11 動力炉・核燃料開発事業団 Method for separating and recovering Pu and Np from nitric acid solution containing Pu and Np
JPH07140293A (en) * 1993-11-16 1995-06-02 Toshiba Corp Recovery method of transuranic element from high level radioactive waste liquid
JP3319657B2 (en) * 1994-07-26 2002-09-03 株式会社東芝 How to convert transuranium oxalate into chloride
JP2948166B2 (en) * 1997-04-04 1999-09-13 核燃料サイクル開発機構 Recovery method of transuranium element from spent nuclear fuel
JPH1184073A (en) * 1997-09-11 1999-03-26 Hitachi Ltd Method and device for reprocessing spent nuclear fuel
FR2803283B1 (en) * 2000-01-03 2002-03-29 Cogema PROCESS AND DEVICE FOR THE CONTINUOUS CONVERSION OF PLUTONIUM OXALATE TO PLUTONIUM OXIDE
JP3549865B2 (en) * 2001-11-28 2004-08-04 核燃料サイクル開発機構 Separation and recovery method of rare element FP in spent nuclear fuel and nuclear power generation-fuel cell power generation symbiosis system using the same
US20080190777A1 (en) * 2004-09-09 2008-08-14 British Titanium Plc. Electro-Deoxidation Method, Apparatus and Product
FR2880180B1 (en) * 2004-12-29 2007-03-02 Cogema IMPROVEMENT OF THE PUREX PROCESS AND ITS USES
FR2901627B1 (en) * 2006-05-24 2009-05-01 Commissariat Energie Atomique PROCESS FOR THE REHABILITATION OF USEFUL NUCLEAR FUEL AND THE PREPARATION OF A MIXED OXIDE OF URANIUM AND PLUTONIUM
WO2008105928A2 (en) * 2006-09-08 2008-09-04 Michael Ernest Johnson Process for treating compositions containing uranium and plutonium
JP4928917B2 (en) * 2006-11-27 2012-05-09 株式会社東芝 Spent oxide nuclear fuel reduction device and lithium regenerative electrolysis device

Also Published As

Publication number Publication date
GB2461370B (en) 2010-10-20
CN101593566B (en) 2012-08-29
FR2931989A1 (en) 2009-12-04
US20090294299A1 (en) 2009-12-03
JP5193687B2 (en) 2013-05-08
RU2403634C1 (en) 2010-11-10
GB2461370A (en) 2010-01-06
CN101593566A (en) 2009-12-02
JP2009288178A (en) 2009-12-10

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Legal Events

Date Code Title Description
PCNP Patent ceased through non-payment of renewal fee

Effective date: 20220529