DE1926827A1 - Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren - Google Patents

Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren

Info

Publication number
DE1926827A1
DE1926827A1 DE19691926827 DE1926827A DE1926827A1 DE 1926827 A1 DE1926827 A1 DE 1926827A1 DE 19691926827 DE19691926827 DE 19691926827 DE 1926827 A DE1926827 A DE 1926827A DE 1926827 A1 DE1926827 A1 DE 1926827A1
Authority
DE
Germany
Prior art keywords
solution
uranium
extraction
thorium
mol
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.)
Pending
Application number
DE19691926827
Other languages
German (de)
English (en)
Inventor
Merz Dr Erich
Kaiser Dr Guenter
Riedel Dr Hans Juergen
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.)
Forschungszentrum Juelich GmbH
Original Assignee
Kernforschungsanlage Juelich GmbH
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 Kernforschungsanlage Juelich GmbH filed Critical Kernforschungsanlage Juelich GmbH
Priority to DE19691926827 priority Critical patent/DE1926827A1/de
Priority to NL7006446A priority patent/NL7006446A/xx
Priority to FR7019150A priority patent/FR2043695B1/fr
Priority to LU60979D priority patent/LU60979A1/xx
Priority to US4069570 priority patent/US3808320A/en
Priority to GB2526070A priority patent/GB1306408A/en
Priority to JP4491570A priority patent/JPS4811277B1/ja
Priority to BE751022D priority patent/BE751022A/xx
Publication of DE1926827A1 publication Critical patent/DE1926827A1/de
Pending 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
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid 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
    • G21C19/48—Non-aqueous processes
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Extraction Or Liquid Replacement (AREA)
DE19691926827 1969-05-27 1969-05-27 Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren Pending DE1926827A1 (de)

Priority Applications (8)

Application Number Priority Date Filing Date Title
DE19691926827 DE1926827A1 (de) 1969-05-27 1969-05-27 Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren
NL7006446A NL7006446A (enExample) 1969-05-27 1970-05-01
FR7019150A FR2043695B1 (enExample) 1969-05-27 1970-05-26
LU60979D LU60979A1 (enExample) 1969-05-27 1970-05-26
US4069570 US3808320A (en) 1969-05-27 1970-05-26 Method for reprocessing radioactive materials
GB2526070A GB1306408A (en) 1969-05-27 1970-05-26 Reprocessing method for fuel and or breeder elements of nuclear reactors
JP4491570A JPS4811277B1 (enExample) 1969-05-27 1970-05-27
BE751022D BE751022A (fr) 1969-05-27 1970-05-27 Procede de recuperation d'elements combustibles et/ou fertiles destinesa des reacteurs nucleaires

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19691926827 DE1926827A1 (de) 1969-05-27 1969-05-27 Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren

Publications (1)

Publication Number Publication Date
DE1926827A1 true DE1926827A1 (de) 1970-12-03

Family

ID=5735253

Family Applications (1)

Application Number Title Priority Date Filing Date
DE19691926827 Pending DE1926827A1 (de) 1969-05-27 1969-05-27 Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren

Country Status (8)

Country Link
US (1) US3808320A (enExample)
JP (1) JPS4811277B1 (enExample)
BE (1) BE751022A (enExample)
DE (1) DE1926827A1 (enExample)
FR (1) FR2043695B1 (enExample)
GB (1) GB1306408A (enExample)
LU (1) LU60979A1 (enExample)
NL (1) NL7006446A (enExample)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2230040B1 (enExample) * 1973-05-18 1976-05-28 Saint Gobain Techn Nouvelles
GB1501907A (en) * 1974-05-15 1978-02-22 Hobeg Gmbh Working up block form graphite nuclear fuel elements
BE879880A (fr) * 1978-11-09 1980-05-07 Macedo Pedro B Fixation par echange d'ions de matieres toxiques dans une matrice de verre
DE3228979A1 (de) * 1982-08-03 1984-02-09 Alkem Gmbh, 6450 Hanau Verfahren zum aufarbeiten eines kernreaktorbrennstabes
US4443413A (en) * 1983-08-31 1984-04-17 The United States Of America As Represented By The United States Department Of Energy Separation of uranium from technetium in recovery of spent nuclear fuel
GB9507644D0 (en) * 1995-04-12 1995-06-14 British Nuclear Fuels Plc Method of processing oxide nuclear fuel
US8571167B2 (en) * 2009-06-01 2013-10-29 Advanced Reactor Concepts LLC Particulate metal fuels used in power generation, recycling systems, and small modular reactors
US9008259B2 (en) 2010-01-13 2015-04-14 Advanced Reactor Concepts LLC Sheathed, annular metal nuclear fuel
WO2011142869A2 (en) 2010-02-22 2011-11-17 Advanced Reactor Concepts LLC Small, fast neutron spectrum nuclear power plant with a long refueling interval
CN106663475A (zh) 2014-04-14 2017-05-10 先进核反应堆概念有限责任公司 分散在金属合金基质中的陶瓷核燃料
WO2016018939A2 (en) * 2014-07-29 2016-02-04 University Of Iowa Research Foundation Methods for separating mixtures

Also Published As

Publication number Publication date
GB1306408A (en) 1973-02-14
FR2043695B1 (enExample) 1974-03-01
US3808320A (en) 1974-04-30
NL7006446A (enExample) 1970-12-01
FR2043695A1 (enExample) 1971-02-19
BE751022A (fr) 1970-11-03
JPS4811277B1 (enExample) 1973-04-12
LU60979A1 (enExample) 1970-07-28

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