FR1294512A - Process for extracting uranium from zirconium-uranium nuclear fuels - Google Patents

Process for extracting uranium from zirconium-uranium nuclear fuels

Info

Publication number
FR1294512A
FR1294512A FR867299A FR867299A FR1294512A FR 1294512 A FR1294512 A FR 1294512A FR 867299 A FR867299 A FR 867299A FR 867299 A FR867299 A FR 867299A FR 1294512 A FR1294512 A FR 1294512A
Authority
FR
France
Prior art keywords
uranium
zirconium
extracting
nuclear fuels
fuels
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
FR867299A
Other languages
French (fr)
Inventor
Theodore Arthur Gens
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 US4170660 external-priority patent/US3043653A/en
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Priority to FR867299A priority Critical patent/FR1294512A/en
Application granted granted Critical
Publication of FR1294512A publication Critical patent/FR1294512A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
    • 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
    • C22B60/0208—Obtaining thorium, uranium, or other actinides obtaining uranium preliminary treatment of ores or scrap
    • 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
    • C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
    • 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

  • Engineering & Computer Science (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
FR867299A 1960-07-08 1961-07-07 Process for extracting uranium from zirconium-uranium nuclear fuels Expired FR1294512A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR867299A FR1294512A (en) 1960-07-08 1961-07-07 Process for extracting uranium from zirconium-uranium nuclear fuels

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US4170660 US3043653A (en) 1960-07-08 1960-07-08 Recovery of uranium from zirconiumuranium nuclear fuels
FR867299A FR1294512A (en) 1960-07-08 1961-07-07 Process for extracting uranium from zirconium-uranium nuclear fuels

Publications (1)

Publication Number Publication Date
FR1294512A true FR1294512A (en) 1962-05-26

Family

ID=26191377

Family Applications (1)

Application Number Title Priority Date Filing Date
FR867299A Expired FR1294512A (en) 1960-07-08 1961-07-07 Process for extracting uranium from zirconium-uranium nuclear fuels

Country Status (1)

Country Link
FR (1) FR1294512A (en)

Similar Documents

Publication Publication Date Title
CH395951A (en) Process for extracting uranium from aqueous solutions containing uranium
FR1220330A (en) Process for extracting elements from mixtures
BE593730A (en) New devices for extracting heat from nuclear reactor fuel elements using transverse fins
CH443240A (en) Process for extracting plutonium, uranium or thorium from a solution of a salt of one of said metals and of an amine salt
FR1294512A (en) Process for extracting uranium from zirconium-uranium nuclear fuels
FR1224953A (en) Uranium recovery
DK104950C (en) Process for recovering relaxin in the form of a phosphorylated carbohydrate-relaxin complex from animal ovaries using extraction with mineral acid and acetone.
FR1242591A (en) Uranium recovery process
FR1178791A (en) Uranium recovery process
FR1272566A (en) Process for the extraction of plutonium from aqueous solutions of irradiated fuels
FR1362865A (en) Process for recovering plutonium from nuclear fuels
FR1241470A (en) Plutonium extraction process
FR1318427A (en) Improvement in the process of extracting uranium from its ores
DK97995C (en) Process for extracting plutonium from aqueous solutions of nuclear fuel.
FR1303476A (en) Liquid-liquid extraction process for the recovery of uranium
BE586510A (en) Plutonium extraction process
FR78150E (en) New process and devices for extracting heat from nuclear reactor fuel elements using transverse fins
FR79227E (en) New process and devices for extracting heat from nuclear reactor fuel elements using transverse fins
FR1203166A (en) Earthmoving process using nuclear explosions
BE602210A (en) Gallium extraction process.
FR1299510A (en) Apparatus for extracting gaseous components from solid fuels
FR1336526A (en) Improved process for extracting plant material
FR1200807A (en) Process for separating plutonium from uranium
FR1293823A (en) Uranium oxides separation process
BE605406A (en) Uranium oxides separation process