GB2534432B - Method for seperating actinides and apparatus for seperating actinides - Google Patents

Method for seperating actinides and apparatus for seperating actinides

Info

Publication number
GB2534432B
GB2534432B GB1510669.3A GB201510669A GB2534432B GB 2534432 B GB2534432 B GB 2534432B GB 201510669 A GB201510669 A GB 201510669A GB 2534432 B GB2534432 B GB 2534432B
Authority
GB
United Kingdom
Prior art keywords
seperating
actinides
seperating actinides
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
GB1510669.3A
Other versions
GB2534432A (en
GB201510669D0 (en
Inventor
Watanabe Daisuke
Kani Yuko
Sasahira Akira
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Publication of GB201510669D0 publication Critical patent/GB201510669D0/en
Publication of GB2534432A publication Critical patent/GB2534432A/en
Application granted granted Critical
Publication of GB2534432B publication Critical patent/GB2534432B/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

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
    • 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
    • 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
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange
    • G21F9/125—Processing by absorption; by adsorption; by ion-exchange by solvent extraction
    • 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)
  • Extraction Or Liquid Replacement (AREA)
GB1510669.3A 2014-06-25 2015-06-17 Method for seperating actinides and apparatus for seperating actinides Expired - Fee Related GB2534432B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2014129805A JP2016008891A (en) 2014-06-25 2014-06-25 Separation method of actinide and separation unit of actinide

Publications (3)

Publication Number Publication Date
GB201510669D0 GB201510669D0 (en) 2015-07-29
GB2534432A GB2534432A (en) 2016-07-27
GB2534432B true GB2534432B (en) 2017-06-07

Family

ID=53784904

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1510669.3A Expired - Fee Related GB2534432B (en) 2014-06-25 2015-06-17 Method for seperating actinides and apparatus for seperating actinides

Country Status (3)

Country Link
JP (1) JP2016008891A (en)
FR (1) FR3023052A1 (en)
GB (1) GB2534432B (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2017145352A1 (en) * 2016-02-26 2017-08-31 株式会社日立製作所 Method for separating minor actinides and apparatus for separating minor actinides
CN107021537A (en) * 2017-03-14 2017-08-08 北京惠宇乐邦环保科技有限公司 A kind of naphthoic acid of 2 hydroxyl 3 produces the processing method of waste water
US11427480B2 (en) 2019-03-29 2022-08-30 The Board Of Regents Of The Nevada System Of Higher Education On Behalf Of The University Of Nevada Conversion of uranium hexafluoride and recovery of uranium from ionic liquids
EP4077219A4 (en) * 2020-03-06 2024-02-21 The Board of Regents of The Nevada System of Higher Education on behalf of the University of Nevada, Las Vegas Stoichiometric recovery of uf4 from uf6 dissolved in ionic liquids
CN112680609B (en) * 2020-12-14 2022-06-03 中国人民解放军63653部队 Plutonium recovery ionic liquid extractant and method for extracting and separating plutonium from plutonium-containing waste liquid
CN113209667B (en) * 2021-03-30 2022-04-12 浙江大学 Method for extracting and separating metal oxometallate by ionic liquid/alkali aqueous two-phase system

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1999041752A1 (en) * 1998-02-11 1999-08-19 British Nuclear Fuels Plc Nuclear fuel reprocessing
US20090184051A1 (en) * 2006-04-19 2009-07-23 Xavier Heres Grouped separation of actinides from a highly acidic aqueous phase
WO2015091791A1 (en) * 2013-12-20 2015-06-25 Commissariat à l'énergie atomique et aux énergies alternatives Method for processing spent nuclear fuel comprising a step of decontaminating the uranium (vi) into at least one actinide (iv) by complexing this actinide (iv)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2015059777A1 (en) * 2013-10-23 2015-04-30 株式会社日立製作所 Method for separating actinide and device for treating spent fuel

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1999041752A1 (en) * 1998-02-11 1999-08-19 British Nuclear Fuels Plc Nuclear fuel reprocessing
US20090184051A1 (en) * 2006-04-19 2009-07-23 Xavier Heres Grouped separation of actinides from a highly acidic aqueous phase
WO2015091791A1 (en) * 2013-12-20 2015-06-25 Commissariat à l'énergie atomique et aux énergies alternatives Method for processing spent nuclear fuel comprising a step of decontaminating the uranium (vi) into at least one actinide (iv) by complexing this actinide (iv)

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
Journal of Radioanalytical and Nuclear Chemistry, Vol 288, June 2011, Pribylova GA, "Influence of ionic liquids on actinides extraction by diphenyl(dibutyl)carbamoylmethylphosphine oxide in different solvents from nitric acid solution", pages 693-697. *
Journal of Radioanalytical and Nuclear Chemistry, vol 295, 2013, Pribylova G.A. et al., "Effect of ionic liquids on the extraction of americium by diphenyl (dibutyl) carbamoylmethyl phosphine oxide in dichloroethane from nitric acid solutions", pages 83-87. *

Also Published As

Publication number Publication date
JP2016008891A (en) 2016-01-18
GB2534432A (en) 2016-07-27
FR3023052A1 (en) 2016-01-01
GB201510669D0 (en) 2015-07-29

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Legal Events

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

Effective date: 20190617