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

    • 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)
LU60979D 1969-05-27 1970-05-26 LU60979A1 (en:Method)

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 (en:Method) 1970-07-28

Family

ID=5735253

Family Applications (1)

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

Country Status (8)

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

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2230040B1 (en:Method) * 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
US8767902B2 (en) 2010-02-22 2014-07-01 Advanced Reactor Concepts LLC Small, fast neutron spectrum nuclear power plant with a long refueling interval
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
FR2043695B1 (en:Method) 1974-03-01
NL7006446A (en:Method) 1970-12-01
BE751022A (fr) 1970-11-03
JPS4811277B1 (en:Method) 1973-04-12
GB1306408A (en) 1973-02-14
US3808320A (en) 1974-04-30
FR2043695A1 (en:Method) 1971-02-19
DE1926827A1 (de) 1970-12-03

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