LU60979A1 - - Google Patents

Info

Publication number
LU60979A1
LU60979A1 LU60979DA LU60979A1 LU 60979 A1 LU60979 A1 LU 60979A1 LU 60979D A LU60979D A LU 60979DA LU 60979 A1 LU60979 A1 LU 60979A1
Authority
LU
Luxembourg
Application number
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 filed Critical
Publication of LU60979A1 publication Critical patent/LU60979A1/xx

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48Non-aqueous processes
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, 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)
  • Manufacture And Refinement Of Metals (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Extraction Or Liquid Replacement (AREA)
LU60979D 1969-05-27 1970-05-26 LU60979A1 (xx)

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
LU60979A1 true LU60979A1 (xx) 1970-07-28

Family

ID=5735253

Family Applications (1)

Application Number Title Priority Date Filing Date
LU60979D LU60979A1 (xx) 1969-05-27 1970-05-26

Country Status (8)

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

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2230040B1 (xx) * 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
WO2011088116A1 (en) 2010-01-13 2011-07-21 Advanced Reactor Concepts LLC Sheathed, annular metal nuclear fuel
RU2596160C2 (ru) 2010-02-22 2016-08-27 Эдвансд Риэктор Консептс Ллк Небольшая атомная электростанция на быстрых нейтронах с длительным интервалом замены топлива
CA3194114A1 (en) 2014-04-14 2015-10-22 Advanced Reactor Concepts LLC Ceramic nuclear fuel dispersed in a metallic alloy matrix
WO2016018939A2 (en) * 2014-07-29 2016-02-04 University Of Iowa Research Foundation Methods for separating mixtures

Also Published As

Publication number Publication date
NL7006446A (xx) 1970-12-01
FR2043695A1 (xx) 1971-02-19
US3808320A (en) 1974-04-30
JPS4811277B1 (xx) 1973-04-12
GB1306408A (en) 1973-02-14
DE1926827A1 (de) 1970-12-03
FR2043695B1 (xx) 1974-03-01
BE751022A (fr) 1970-11-03

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