FR1251767A - Procédé de dissolution d'éléments de combustible contenant du zirconium - Google Patents

Procédé de dissolution d'éléments de combustible contenant du zirconium

Info

Publication number
FR1251767A
FR1251767A FR821965A FR821965A FR1251767A FR 1251767 A FR1251767 A FR 1251767A FR 821965 A FR821965 A FR 821965A FR 821965 A FR821965 A FR 821965A FR 1251767 A FR1251767 A FR 1251767A
Authority
FR
France
Prior art keywords
fuel elements
containing zirconium
elements containing
dissolving fuel
dissolving
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
Application number
FR821965A
Other languages
English (en)
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.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
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
Priority claimed from US80455359 external-priority patent/US3012849A/en
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Priority to FR821965A priority Critical patent/FR1251767A/fr
Application granted granted Critical
Publication of FR1251767A publication Critical patent/FR1251767A/fr
Expired 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
    • G21C19/48—Non-aqueous processes
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G25/00—Compounds of zirconium
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G25/00—Compounds of zirconium
    • C01G25/04—Halides
    • 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
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/04—Halides of uranium
    • C01G43/06—Fluorides
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/04—Halides of uranium
    • C01G43/06—Fluorides
    • C01G43/063—Hexafluoride (UF6)
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/04—Halides of uranium
    • C01G43/06—Fluorides
    • C01G43/063—Hexafluoride (UF6)
    • C01G43/066—Preparation
    • 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
    • C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/023—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors halogenated ion as active agent
    • 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)
  • Inorganic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
FR821965A 1959-04-06 1960-03-21 Procédé de dissolution d'éléments de combustible contenant du zirconium Expired FR1251767A (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR821965A FR1251767A (fr) 1959-04-06 1960-03-21 Procédé de dissolution d'éléments de combustible contenant du zirconium

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US80455359 US3012849A (en) 1959-04-06 1959-04-06 Dissolution of zirconium-containing fuel elements
FR821965A FR1251767A (fr) 1959-04-06 1960-03-21 Procédé de dissolution d'éléments de combustible contenant du zirconium

Publications (1)

Publication Number Publication Date
FR1251767A true FR1251767A (fr) 1961-01-20

Family

ID=26185376

Family Applications (1)

Application Number Title Priority Date Filing Date
FR821965A Expired FR1251767A (fr) 1959-04-06 1960-03-21 Procédé de dissolution d'éléments de combustible contenant du zirconium

Country Status (1)

Country Link
FR (1) FR1251767A (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2533907A1 (fr) * 1982-10-04 1984-04-06 Pechiney Ugine Kuhlmann Uran Procede de purification de solutions aqueuses uraniferes contenant du zirconium et/ou du hafnium entre autres impuretes

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2533907A1 (fr) * 1982-10-04 1984-04-06 Pechiney Ugine Kuhlmann Uran Procede de purification de solutions aqueuses uraniferes contenant du zirconium et/ou du hafnium entre autres impuretes

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