NL276441A - - Google Patents

Info

Publication number
NL276441A
NL276441A NL276441DA NL276441A NL 276441 A NL276441 A NL 276441A NL 276441D A NL276441D A NL 276441DA NL 276441 A NL276441 A NL 276441A
Authority
NL
Netherlands
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.)
Publication date
Publication of NL276441A publication Critical patent/NL276441A/xx

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C—CHEMISTRY; METALLURGY
    • C07—ORGANIC CHEMISTRY
    • C07C—ACYCLIC OR CARBOCYCLIC COMPOUNDS
    • C07C19/00—Acyclic saturated compounds containing halogen atoms
    • C07C19/01—Acyclic saturated compounds containing halogen atoms containing chlorine
    • C07C19/03—Chloromethanes
    • C07C19/04—Chloroform
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
    • 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

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Geology (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
NL276441D 1961-03-30 NL276441A (en:Method)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US9964861 US3148941A (en) 1961-03-30 1961-03-30 Dissolution of uranium-molybdenum reactor fuel elements

Publications (1)

Publication Number Publication Date
NL276441A true NL276441A (en:Method) 1900-01-01

Family

ID=22275993

Family Applications (1)

Application Number Title Priority Date Filing Date
NL276441D NL276441A (en:Method) 1961-03-30

Country Status (4)

Country Link
US (1) US3148941A (en:Method)
DE (1) DE1181190B (en:Method)
GB (1) GB981532A (en:Method)
NL (1) NL276441A (en:Method)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL267653A (en:Method) * 1960-08-03 1900-01-01
US3450639A (en) * 1967-02-20 1969-06-17 Commissariat Energie Atomique Process for the separation of molybdenum from fission product containing solutions
JPS5233280B2 (en:Method) * 1974-02-07 1977-08-26
US4284472A (en) * 1978-10-16 1981-08-18 General Electric Company Method for enhanced control of radioiodine in the production of fission product molybdenum 99
RU2217822C1 (ru) * 2002-04-05 2003-11-27 Федеральное государственное унитарное предприятие "Государственный научный центр РФ Научно-исследовательский институт атомных реакторов" Аппарат для непрерывного "сухого" хлорирования диоксида плутония
WO2011156446A2 (en) * 2010-06-09 2011-12-15 General Atomics Methods and apparatus for selective gaseous extraction of molybdenum-99 and other fission product radioisotopes
RU2613352C1 (ru) * 2016-04-11 2017-03-16 Федеральное государственное унитарное предприятие "Научно-исследовательский институт Научно-производственное объединение "ЛУЧ" (ФГУП "НИИ НПО "ЛУЧ") Способ переработки уран-циркониевых отходов

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2582941A (en) * 1944-10-12 1952-01-15 Coleman D Wilder Processes of producing uranium chlorides
US2865704A (en) * 1947-01-08 1958-12-23 Arthur H Jaffey Method of separating uranium, plutonium, and fission products by bromination and distillation
US2910344A (en) * 1948-04-09 1959-10-27 Norman R Davidson Method of preparing uf
US2887356A (en) * 1955-09-21 1959-05-19 Horizons Titanium Corp Production of oxygen-free and anhydrous fused salt electrolyte from oxygen containing compounds of uranium
NL267653A (en:Method) 1960-08-03 1900-01-01

Also Published As

Publication number Publication date
US3148941A (en) 1964-09-15
DE1181190B (de) 1964-11-12
GB981532A (en) 1965-01-27

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