GB2343899B - Electrolytic treatment method of zirconium and apparatus therefor - Google Patents

Electrolytic treatment method of zirconium and apparatus therefor

Info

Publication number
GB2343899B
GB2343899B GB9927452A GB9927452A GB2343899B GB 2343899 B GB2343899 B GB 2343899B GB 9927452 A GB9927452 A GB 9927452A GB 9927452 A GB9927452 A GB 9927452A GB 2343899 B GB2343899 B GB 2343899B
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.)
Expired - Fee Related
Application number
GB9927452A
Other versions
GB2343899A (en
GB9927452D0 (en
Inventor
Michitaka Saso
Masaaki Kaneko
Shinya Miyamoto
Yoshikazu Matsubayashi
Yasushi Yamaguchi
Atsushi Nakajima
Nobuyuki Ikenaga
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 GB9927452D0 publication Critical patent/GB9927452D0/en
Publication of GB2343899A publication Critical patent/GB2343899A/en
Application granted granted Critical
Publication of GB2343899B publication Critical patent/GB2343899B/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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)
GB9927452A 1998-11-19 1999-11-19 Electrolytic treatment method of zirconium and apparatus therefor Expired - Fee Related GB2343899B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP32910398A JP2000144274A (en) 1998-11-19 1998-11-19 Electrolytic method of zirconium waster and device therefor

Publications (3)

Publication Number Publication Date
GB9927452D0 GB9927452D0 (en) 2000-01-19
GB2343899A GB2343899A (en) 2000-05-24
GB2343899B true GB2343899B (en) 2001-05-16

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 Before (1)

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

Country Status (3)

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

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104109884A (en) * 2014-07-18 2014-10-22 中信锦州金属股份有限公司 Method for preparing metal zirconium powder with molten salt electrolysis method

Citations (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1067911A (en) * 1963-10-01 1967-05-10 Commissariat Energie Atomique Improvements in or relating to the electrolytic etching of zirconium and zirconium-base alloys
US3932225A (en) * 1971-11-03 1976-01-13 Hahn-Meitner-Institut Fur Kernforschung Berlin Gmbh Process for separately recovering uranium, transuranium elements, and fission products of uranium from atomic reactor fuel
EP0089185A2 (en) * 1982-03-11 1983-09-21 Exxon Nuclear Company Inc. Dissolution of Pu02 or Np02 using electrolytically regenerated reagents
GB2152271A (en) * 1983-12-22 1985-07-31 Kernforschungsz Karlsruhe Improvements in the separation of uranium, plutonium and other radioactive/fissionable materials
US4741810A (en) * 1983-12-14 1988-05-03 Kernforschugszentrum Karlsruhe Gmbh Process for reductive plutonium stripping from an organic reprocessing solution into an aqueous, nitric acid solution by use of an electrolytic current
US4749519A (en) * 1984-03-27 1988-06-07 Commissariat A L'energie Atomique Process for the recovery of 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
JPH01147398A (en) * 1987-12-02 1989-06-09 Hitachi Ltd Nuclear fuel reprocessing plant and its production
EP0324862A1 (en) * 1987-07-29 1989-07-26 Hitachi, Ltd. Nuclear fuel reprocessing plant
GB2220602A (en) * 1988-03-10 1990-01-17 Atomic Energy Authority Uk Method of, and apparatus for, cutting
JPH05188187A (en) * 1992-01-14 1993-07-30 Power Reactor & Nuclear Fuel Dev Corp Recovery of valuable metal from nuclear-fuel reprocessing dissolution liquid
EP0638907A1 (en) * 1993-08-13 1995-02-15 Doryokuro Kakunenryo Kaihatsu Jigyodan Method of separating and recovering plutonium and neptunium from a nitric acid solution
US5609745A (en) * 1995-03-15 1997-03-11 Commissariat A L'energie Atomique Process for the electrochemical oxidation of Am(III) to Am(VI) usable for separating americium from spent nuclear fuel reprocessing solutions
GB2323854A (en) * 1997-04-04 1998-10-07 Doryokuro Kakunenryo Method of recovering uranium and transuranic elements from spent nuclear fuel
WO1999034369A1 (en) * 1997-12-29 1999-07-08 Commissariat A L'energie Atomique Method and device for oxidising one or several actinides stabilised in reduced form with one or several anti-nitrous agents in concentrated nitric solution

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2081176A1 (en) * 1970-03-13 1971-12-03 Commissariat Energie Atomique Extraction of irradiated fuel elements - for recovery of fissile material and fission products
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

Patent Citations (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1067911A (en) * 1963-10-01 1967-05-10 Commissariat Energie Atomique Improvements in or relating to the electrolytic etching of zirconium and zirconium-base alloys
US3932225A (en) * 1971-11-03 1976-01-13 Hahn-Meitner-Institut Fur Kernforschung Berlin Gmbh Process for separately recovering uranium, transuranium elements, and fission products of uranium from atomic reactor fuel
EP0089185A2 (en) * 1982-03-11 1983-09-21 Exxon Nuclear Company Inc. Dissolution of Pu02 or Np02 using electrolytically regenerated reagents
US4741810A (en) * 1983-12-14 1988-05-03 Kernforschugszentrum Karlsruhe Gmbh Process for reductive plutonium stripping from an organic reprocessing solution into an aqueous, nitric acid solution by use of an electrolytic current
GB2152271A (en) * 1983-12-22 1985-07-31 Kernforschungsz Karlsruhe Improvements in the separation of uranium, plutonium and other radioactive/fissionable materials
US4749519A (en) * 1984-03-27 1988-06-07 Commissariat A L'energie Atomique Process for the recovery of 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
EP0324862A1 (en) * 1987-07-29 1989-07-26 Hitachi, Ltd. Nuclear fuel reprocessing plant
JPH01147398A (en) * 1987-12-02 1989-06-09 Hitachi Ltd Nuclear fuel reprocessing plant and its production
GB2220602A (en) * 1988-03-10 1990-01-17 Atomic Energy Authority Uk Method of, and apparatus for, cutting
JPH05188187A (en) * 1992-01-14 1993-07-30 Power Reactor & Nuclear Fuel Dev Corp Recovery of valuable metal from nuclear-fuel reprocessing dissolution liquid
EP0638907A1 (en) * 1993-08-13 1995-02-15 Doryokuro Kakunenryo Kaihatsu Jigyodan Method of separating and recovering plutonium and neptunium from a nitric acid solution
US5609745A (en) * 1995-03-15 1997-03-11 Commissariat A L'energie Atomique Process for the electrochemical oxidation of Am(III) to Am(VI) usable for separating americium from spent nuclear fuel reprocessing solutions
GB2323854A (en) * 1997-04-04 1998-10-07 Doryokuro Kakunenryo Method of recovering uranium and transuranic elements from spent nuclear fuel
WO1999034369A1 (en) * 1997-12-29 1999-07-08 Commissariat A L'energie Atomique Method and device for oxidising one or several actinides stabilised in reduced form with one or several anti-nitrous agents in concentrated nitric solution

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
WPI Accession no 89-210258 & JP 01 147 398 A *
WPI Accession no 93-275244 & JP 05 188 187 A *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104109884A (en) * 2014-07-18 2014-10-22 中信锦州金属股份有限公司 Method for preparing metal zirconium powder with molten salt electrolysis method
CN104109884B (en) * 2014-07-18 2016-10-19 中信锦州金属股份有限公司 A kind of fused salt electrolysis process prepares the method for metal zirconium powder

Also Published As

Publication number Publication date
GB2343899A (en) 2000-05-24
JP2000144274A (en) 2000-05-26
GB9927452D0 (en) 2000-01-19
FR2786205A1 (en) 2000-05-26
FR2786205B1 (en) 2005-09-23
GB9927217D0 (en) 2000-01-12

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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: 20151119