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UST970007I4 - Uranium recovery from wet-process phosphoric acid - Google Patents

Uranium recovery from wet-process phosphoric acid Download PDF

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Publication number
UST970007I4
UST970007I4 US05/781,216 US78121677A UST970007I4 US T970007 I4 UST970007 I4 US T970007I4 US 78121677 A US78121677 A US 78121677A US T970007 I4 UST970007 I4 US T970007I4
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US
United States
Prior art keywords
acid
phosphoric acid
uranium
methanol
miscible solvent
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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.)
Pending
Application number
US05/781,216
Inventor
John F. McCullough
John F. Phillips, Jr.
Leslie R. Tate
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.)
Tennessee Valley Authority (ATV)
Original Assignee
Tennessee Valley Authority (ATV)
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 Tennessee Valley Authority (ATV) filed Critical Tennessee Valley Authority (ATV)
Priority to US05/781,216 priority Critical patent/UST970007I4/en
Priority to US05/827,517 priority patent/US4180545A/en
Application granted granted Critical
Publication of UST970007I4 publication Critical patent/UST970007I4/en
Pending legal-status Critical Current

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    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/026Obtaining 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
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B25/00Phosphorus; Compounds thereof
    • C01B25/16Oxyacids of phosphorus; Salts thereof
    • C01B25/18Phosphoric acid
    • C01B25/234Purification; Stabilisation; Concentration

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  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Environmental & Geological Engineering (AREA)
  • Inorganic Chemistry (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

a method of recovering uranium from wet-process phosphoric acid wherein the acid is treated with a mixture of an ammonium salt or ammonia, a metallic reducing agent such as iron, aluminum or zinc, and then a miscible solvent such as methanol. The precipitated solids, which are separated from the purified phosphoric acid, consist of a mixture of metal phosphates and uranium. This solid is dissolved in acid and the uranium recovered from the solution by liquid-liquid solvent extraction. The miscible solvent and some water are distilled away from the purified phosphoric acid. The distillate is rectified, the water discarded, and the miscible solvent recovered for recycle.
When the miscible solvent is methanol, the optimum ranges of ammonia and methanol are 0.05 to 0.20 gram atom nitrogen per gram atom phosphorus and 1.93 to 3.15 pounds methanol per pound of orthophosphoric acid. The amount of reducing agent added should be sufficient to reduce all uraniun to U(IV). Under these conditions, >99 percent of the uranium is precipitated from the wet-process acid. About 90 percent of the phosphorus in the acid is recovered as purified phosphoric acid.
US05/781,216 1977-03-25 1977-03-25 Uranium recovery from wet-process phosphoric acid Pending UST970007I4 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
US05/781,216 UST970007I4 (en) 1977-03-25 1977-03-25 Uranium recovery from wet-process phosphoric acid
US05/827,517 US4180545A (en) 1977-03-25 1977-08-25 Uranium recovery from wet-process phosphoric acid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/781,216 UST970007I4 (en) 1977-03-25 1977-03-25 Uranium recovery from wet-process phosphoric acid

Related Child Applications (1)

Application Number Title Priority Date Filing Date
US05/827,517 Continuation US4180545A (en) 1977-03-25 1977-08-25 Uranium recovery from wet-process phosphoric acid

Publications (1)

Publication Number Publication Date
UST970007I4 true UST970007I4 (en) 1978-05-02

Family

ID=25122049

Family Applications (1)

Application Number Title Priority Date Filing Date
US05/781,216 Pending UST970007I4 (en) 1977-03-25 1977-03-25 Uranium recovery from wet-process phosphoric acid

Country Status (1)

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US (1) UST970007I4 (en)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0015589A1 (en) * 1979-01-25 1980-09-17 Stamicarbon B.V. Process for recovering a uranium-containing concentrate and purified phosphoric acid from wet-process phosphoric acid, and products thus obtained
EP0023057A1 (en) * 1979-07-24 1981-01-28 Stamicarbon B.V. Process for preparing phosphates and a uranium-containing concentrate from wet-process phosphoric acid, as well as phosphates and uranium-containing concentrate obtained with application of this process
EP0031793A2 (en) * 1979-12-03 1981-07-08 Schweizerische Aluminium AG Process for producing phosphoric acid during which uranium in a recoverable state is obtained
US4301122A (en) 1978-10-19 1981-11-17 Mobil Oil Corporation Recovery of uranium from phosphate ores
US4311676A (en) 1978-09-08 1982-01-19 Minemet Recherche Process for the recovery of uranium contained in phosphated compounds
US4399110A (en) 1980-06-11 1983-08-16 Chemische Werke Huls Aktiengesellschaft Process for reducing the radioactivity of calcium sulfate prepared from phosphate rock
US5188736A (en) * 1991-08-27 1993-02-23 Institute Of Nuclear Energy Research Process for the separation and recovery of extractant from spent solvent
US8354567B2 (en) 2008-01-30 2013-01-15 David Donald Leavitt Destruction of mixed radioactive waste by catalyzed chemical oxidation

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4311676A (en) 1978-09-08 1982-01-19 Minemet Recherche Process for the recovery of uranium contained in phosphated compounds
US4301122A (en) 1978-10-19 1981-11-17 Mobil Oil Corporation Recovery of uranium from phosphate ores
EP0015589A1 (en) * 1979-01-25 1980-09-17 Stamicarbon B.V. Process for recovering a uranium-containing concentrate and purified phosphoric acid from wet-process phosphoric acid, and products thus obtained
US4514365A (en) 1979-01-25 1985-04-30 Stamicarbon B.V. Process for recovering a uranium-containing concentrate and purified phosphoric acid from a wet process phosphoric acid containing uranium
EP0023057A1 (en) * 1979-07-24 1981-01-28 Stamicarbon B.V. Process for preparing phosphates and a uranium-containing concentrate from wet-process phosphoric acid, as well as phosphates and uranium-containing concentrate obtained with application of this process
JPS5626707A (en) * 1979-07-24 1981-03-14 Stamicarbon Method of manufacturing phsphate and uraniummcontaining condensate from wet process phosphoric acid and phosphate and uraniumm containing condensate obtained thereby
EP0031793A2 (en) * 1979-12-03 1981-07-08 Schweizerische Aluminium AG Process for producing phosphoric acid during which uranium in a recoverable state is obtained
EP0031793A3 (en) * 1979-12-03 1981-07-22 Schweizerische Aluminium Ag Process for producing phosphoric acid during which uranium in a recoverable state is obtained
US4399110A (en) 1980-06-11 1983-08-16 Chemische Werke Huls Aktiengesellschaft Process for reducing the radioactivity of calcium sulfate prepared from phosphate rock
US5188736A (en) * 1991-08-27 1993-02-23 Institute Of Nuclear Energy Research Process for the separation and recovery of extractant from spent solvent
US8354567B2 (en) 2008-01-30 2013-01-15 David Donald Leavitt Destruction of mixed radioactive waste by catalyzed chemical oxidation

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