GB801379A - Recovery of plutonium - Google Patents

Recovery of plutonium

Info

Publication number
GB801379A
GB801379A GB950044A GB950044A GB801379A GB 801379 A GB801379 A GB 801379A GB 950044 A GB950044 A GB 950044A GB 950044 A GB950044 A GB 950044A GB 801379 A GB801379 A GB 801379A
Authority
GB
United Kingdom
Prior art keywords
plutonium
adsorbent
fission products
solution
diatomaceous earth
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
GB950044A
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of GB801379A publication Critical patent/GB801379A/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
    • C22B60/0217—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
    • C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
    • 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
    • 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

Abstract

Plutonium is recovered from an aqueous solution in which it is present together with uranium or fission products or both, by preferential adsorption of plutonium on diatomaceous earth, fuller's earth, silica gel, or magnesium silicate. Neutron-irradiated uranium may be dissolved in nitric acid and the solution contacted with the adsorbent, preferably at a pH of 2.3-3.7. The concentration of uranyl nitrate in the solution is preferably below 30 per cent. Plutonium may be eluted from the adsorbent with 6N nitric acid of the fission products, a high proportion of columbium is adsorbed, lesser amounts of zirconium, and very small amounts of other fission products, e.g. barium and lanthanum. To separate columbium and zirconium from plutonium, the plutonium may be precipitated in its lower oxidation state with fluoride ion; alternatively the plutonium may be eluted from the adsorbent with ammonium carbonate solution, leaving some fission products behind. Experiments are described showing (a) the suitability of diatomaceous earth for re-use as an adsorbent after elution with nitric acid; (b) the effect on the amount of plutonium adsorbed of the pH of the aqueous solution and the concentration of uranyl nitrate; (c) the maximum pH to which uranyl nitrate solutions of different concentration may be raised without causing precipitation; (d) the raising of the pH of the first portion of a solution passed through a column of diatomaceous earth; (e) the strength of acid necessary for elution of the plutonium; (f) the effect of bombardment by deuterous of the diatomaceous earth adsorbent; (g) the amounts of plutonium and fission products adsorbed on a column of silica gel.
GB950044A 1943-05-18 1944-05-17 Recovery of plutonium Expired GB801379A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US48742843 US2819144A (en) 1943-05-18 1943-05-18 Separation of plutonium from uranium and fission products by adsorption

Publications (1)

Publication Number Publication Date
GB801379A true GB801379A (en) 1958-09-10

Family

ID=23935685

Family Applications (1)

Application Number Title Priority Date Filing Date
GB950044A Expired GB801379A (en) 1943-05-18 1944-05-17 Recovery of plutonium

Country Status (2)

Country Link
US (1) US2819144A (en)
GB (1) GB801379A (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2992889A (en) * 1945-09-05 1961-07-18 Davies Thomas Harrison Method for separating plutonium and fission products employing an oxide as a carrierfor fission products
US2890932A (en) * 1951-05-07 1959-06-16 Charles S Lowe Separation by adsorption
US2869983A (en) * 1957-11-13 1959-01-20 Dieter M Gruen Separation of metal salts by adsorption
US2942943A (en) * 1958-04-30 1960-06-28 Margaret W Greene Process for separating iodine-132 from fission products
BE653712A (en) * 1963-10-01
FR2480019B1 (en) * 1980-04-08 1986-11-14 Etu En Nucleaire Centre PROCESS FOR EXTRACTING FLUORIDE IONS FROM A NUCLEAR FUEL SOLUTION
DE3346405A1 (en) * 1983-12-22 1985-07-04 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR THE IMPROVED SEPARATION OF THE RECOVERY OF THE URAN AND PLUTONIUM FUELS AND THE IMPROVED SEPARATION OF THE FUELS TO BE RECOVERED FROM HIM IN A REPROCESSING PROCESS

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1142153A (en) * 1915-06-08 Erich Ebler Manufacture, isolation, and enrichment of radio-active substances by adsorption from solutions.
US2204072A (en) * 1940-06-11 Certificate op correction
US1059531A (en) * 1912-03-04 1913-04-22 Erich Ebler Process for the preparation, isolation, and enrichment of radium and other radio-active substances.
US1934838A (en) * 1930-04-14 1933-11-14 Ig Farbenindustrie Ag Production of hydrocyanic acid
US2129733A (en) * 1936-10-07 1938-09-13 Standard Oil Dev Co Production of liquid hydrocarbons from gaseous olefines

Also Published As

Publication number Publication date
US2819144A (en) 1958-01-07

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