GB9927217D0 - Electrolytic treatment method of zirconium and apparatus therefor - Google Patents

Electrolytic treatment method of zirconium and apparatus therefor

Info

Publication number
GB9927217D0
GB9927217D0 GB9927217A GB9927217A GB9927217D0 GB 9927217 D0 GB9927217 D0 GB 9927217D0 GB 9927217 A GB9927217 A GB 9927217A GB 9927217 A GB9927217 A GB 9927217A GB 9927217 D0 GB9927217 D0 GB 9927217D0
Authority
GB
United Kingdom
Prior art keywords
zirconium
treatment method
apparatus therefor
electrolytic treatment
electrolytic
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.)
Ceased
Application number
GB9927217A
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 GB9927217D0 publication Critical patent/GB9927217D0/en
Ceased legal-status Critical Current

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
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • 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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • G21C19/38—Chemical means only
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Electrolytic Production Of Non-Metals, Compounds, Apparatuses Therefor (AREA)
  • Water Treatment By Electricity Or Magnetism (AREA)
  • Manufacture And Refinement Of Metals (AREA)
GB9927217A 1998-11-19 1999-11-17 Electrolytic treatment method of zirconium and apparatus therefor Ceased GB9927217D0 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP32910398A JP2000144274A (en) 1998-11-19 1998-11-19 Method and apparatus for electrolytic treatment of zirconium waste

Publications (1)

Publication Number Publication Date
GB9927217D0 true GB9927217D0 (en) 2000-01-12

Family

ID=18217653

Family Applications (2)

Application Number Title Priority Date Filing Date
GB9927217A Ceased GB9927217D0 (en) 1998-11-19 1999-11-17 Electrolytic treatment method of zirconium and apparatus therefor
GB9927452A Expired - Fee Related GB2343899B (en) 1998-11-19 1999-11-19 Electrolytic treatment method of zirconium and apparatus therefor

Family Applications After (1)

Application Number Title Priority Date Filing Date
GB9927452A Expired - Fee Related GB2343899B (en) 1998-11-19 1999-11-19 Electrolytic treatment method of zirconium and apparatus therefor

Country Status (3)

Country Link
JP (1) JP2000144274A (en)
FR (1) FR2786205B1 (en)
GB (2) GB9927217D0 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2235686C1 (en) * 2003-01-04 2004-09-10 Шарыгин Леонид Михайлович Method of preparing spherically granulated zirconium hydroxide or oxide-based materials
CN104109884B (en) * 2014-07-18 2016-10-19 中信锦州金属股份有限公司 A method for preparing metal zirconium powder by molten salt electrolysis

Family Cites Families (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1383839A (en) * 1963-10-01 1965-01-04 Commissariat Energie Atomique Process for electrolytic pickling of zirconium and its alloys and products obtained by this process
FR2081176A1 (en) * 1970-03-13 1971-12-03 Commissariat Energie Atomique Extraction of irradiated fuel elements - for recovery of fissile material and fission products
DE2154655C3 (en) * 1971-11-03 1979-07-26 Hahn-Meitner-Institut Fuer Kernforschung Berlin Gmbh, 1000 Berlin Process for the separation of uranium, transuranium elements and mixtures containing elements occurring as fission products of nuclear fuels by countercurrent or cross-current electrolysis
DE2520869C2 (en) * 1975-05-10 1985-02-07 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Countercurrent extraction column for liquid-liquid extraction of two mutually insoluble phases with simultaneous electrolysis
US4686019A (en) * 1982-03-11 1987-08-11 Exxon Research And Engineering Company Dissolution of PuO2 or NpO2 using electrolytically regenerated reagents
EP0089185A3 (en) * 1982-03-11 1985-12-18 Exxon Nuclear Company Inc. Dissolution of pu02 or np02 using electrolytically regenerated reagents
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
DE3346405A1 (en) * 1983-12-22 1985-07-04 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR THE IMPROVED SEPARATION OF THE RECOVERY OF THE URAN AND PLUTONIUM FUELS AND THE IMPROVED SEPARATION OF THE FUELS TO BE RECOVERED FROM HIM IN A REPROCESSING PROCESS
FR2562314B1 (en) * 1984-03-27 1989-02-17 Commissariat Energie Atomique PROCESS FOR RECOVERING PLUTONIUM CONTAINED IN SOLID WASTE
DE3738996A1 (en) * 1986-12-02 1988-06-30 Robotron Veb K Method and appliance for the deposition of copper from ammoniacal copper chloride solutions
JPS6432197A (en) * 1987-07-29 1989-02-02 Hitachi Ltd Plant for retreatment of nuclear fuel
JPH01147398A (en) * 1987-12-02 1989-06-09 Hitachi Ltd Nuclear fuel reprocessing plant and its production
GB8805752D0 (en) * 1988-03-10 1988-04-07 Atomic Energy Authority Uk Method of cutting
JP2713828B2 (en) * 1992-01-14 1998-02-16 動力炉・核燃料開発事業団 Method for recovering valuable metals from nuclear fuel reprocessing solution
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
FR2731717B1 (en) * 1995-03-15 1997-04-25 Commissariat Energie Atomique PROCESS FOR THE ELECTROCHEMICAL OXIDATION OF AM (VII) TO AM (VI), USEFUL FOR SEPARATING AMERICIUM FROM USED NUCLEAR FUEL PROCESSING SOLUTIONS
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
FR2773176B1 (en) * 1997-12-29 2001-04-27 Commissariat Energie Atomique PROCESS AND DEVICE FOR THE OXIDATION OF ONE OR MORE ACTINIDES STABILIZED IN REDUCED FORM BY ONE OR MORE ANTI-NITROUS AGENTS, IN NITRIC CONCENTRATE

Also Published As

Publication number Publication date
GB2343899A (en) 2000-05-24
FR2786205A1 (en) 2000-05-26
GB9927452D0 (en) 2000-01-19
GB2343899B (en) 2001-05-16
FR2786205B1 (en) 2005-09-23
JP2000144274A (en) 2000-05-26

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Legal Events

Date Code Title Description
AT Applications terminated before publication under section 16(1)