KR830010211A - Recovery method of uranium by magnetic separation - Google Patents

Recovery method of uranium by magnetic separation Download PDF

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Publication number
KR830010211A
KR830010211A KR1019820002264A KR820002264A KR830010211A KR 830010211 A KR830010211 A KR 830010211A KR 1019820002264 A KR1019820002264 A KR 1019820002264A KR 820002264 A KR820002264 A KR 820002264A KR 830010211 A KR830010211 A KR 830010211A
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KR
South Korea
Prior art keywords
uranium
separator
acid solution
nitric acid
ion exchange
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Application number
KR1019820002264A
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Korean (ko)
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KR900000397B1 (en
Inventor
쟌 라호다 에드워드
Original Assignee
디 디 스타크
웨스팅하우스 일렉트릭 코오포레이숀
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Publication of KR830010211A publication Critical patent/KR830010211A/en
Application granted granted Critical
Publication of KR900000397B1 publication Critical patent/KR900000397B1/en

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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
    • 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
    • C22B60/0208Obtaining thorium, uranium, or other actinides obtaining uranium preliminary treatment of ores or scrap
    • 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
    • C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0239Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
    • 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
    • C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0247Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using basic solutions or liquors
    • 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
    • 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
    • C22B60/0265Obtaining 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

Abstract

내용 없음No content

Description

자력분리에 의한 우라늄의 회수방법Recovery method of uranium by magnetic separation

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음Since this is an open matter, no full text was included.

제1도는 탄소여과기와 이온교환을 사용한 우라늄 회수과정을 도해한 약도, 제2도는 질산 세척을 사용한 선택적인 우라늄 회수과정을 도해한 약도.1 is a diagram illustrating a uranium recovery process using carbon filter and ion exchange, and FIG. 2 is a diagram illustrating a selective uranium recovery process using nitric acid washing.

Claims (11)

100ppm 이하의 철을 함유하는 수성 플루오르화 칼슘 슬러리를 높은 변화도를 갖는 분리기를 통과시킨뒤, 상기 슬러리에서 우라늄을 제거하는 것을 특징으로 하는 우라늄의 회수방법.A method for recovering uranium, wherein an aqueous calcium fluoride slurry containing up to 100 ppm of iron is passed through a separator having a high degree of change, and then uranium is removed from the slurry. 제1항에 있어서, 상기 분리기의 자기장을 10킬로 가우스로 한다는 것을 특징으로 하는 방법.The method of claim 1 wherein the magnetic field of the separator is 10 kilo gauss. 제1항 또는 2항에 있어서, pH가 2와 3사이인 질산용액에 의하여 세척되는 분리기로부터 우라늄을 제거하는 것을 특징으로 하는 방법.The method according to claim 1 or 2, characterized in that the uranium is removed from the separator which is washed by a nitric acid solution having a pH between 2 and 3. 제3항에 있어서, 우라늄이 DEPA-TOPO를 사용하여 질산용액에서 용매추출되는 것을 특징으로 하는 방법.4. The method of claim 3, wherein the uranium is solvent extracted from the nitric acid solution using DEPA-TOPO. 제1항 또는 2항에 있어서, 탄산용액의 여과물에 의하여 분리기로부터 우라늄이 제거되는 것을 특징으로 하는 방법.The method according to claim 1 or 2, wherein uranium is removed from the separator by the filtrate of the carbonic acid solution. 제5항에 있어서 탄산용액이 2 내지 5몰의 탄산 암모늄으로부터 제조되어지는 것을 특징으로 하는 방법.The method of claim 5 wherein the carbonate solution is prepared from 2 to 5 moles of ammonium carbonate. 제5항 또는 6항에 있어서, 탄산용액에 포함된 우라늄이 이온교환관에서 제거되는 것을 특징으로 하는 방법.The method of claim 5 or 6, wherein the uranium contained in the carbonic acid solution is removed from the ion exchange tube. 제7항에 있어서, 이온교환관에 있는 우라늄이 질산용액으로 제조되어 진다는 것을 특징으로 하는 방법.8. The method of claim 7, wherein the uranium in the ion exchange tube is made of nitric acid solution. 상기 모든 항에 있어서, 분리기의 두개의 자석극이, 액체 슬러리가 통과하는 다공성강자성매체로 채워지는 것을 특징으로 하는 제조방법.A method according to any of the preceding claims, wherein the two magnet poles of the separator are filled with a porous ferromagnetic medium through which the liquid slurry passes. 제9항에 있어서, 자석극은 3인치이상 떨어지지않고, 코일 지름이 40cm 이하로 되는 것을 특징으로 하는 방법.10. The method of claim 9, wherein the magnet poles are no more than three inches apart and the coil diameter is less than 40 cm. 제9항 또는 10항에 있어서, 50% 보다 큰 공유성을 갖는 스테인레스 강철털이라는 것을 특징으로하는 분리기의 제조방법.11. A method as claimed in claim 9 or 10, characterized in that it is stainless steel hair having a covalentness of greater than 50%. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR8202264A 1981-05-22 1982-05-22 Method of recovering uranium KR900000397B1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
US26668181A 1981-05-22 1981-05-22
US266,681 1981-05-22
US266681 1981-05-22

Publications (2)

Publication Number Publication Date
KR830010211A true KR830010211A (en) 1983-12-26
KR900000397B1 KR900000397B1 (en) 1990-01-25

Family

ID=23015572

Family Applications (1)

Application Number Title Priority Date Filing Date
KR8202264A KR900000397B1 (en) 1981-05-22 1982-05-22 Method of recovering uranium

Country Status (7)

Country Link
EP (1) EP0066419B1 (en)
JP (1) JPS5930651B2 (en)
KR (1) KR900000397B1 (en)
DE (1) DE3272997D1 (en)
ES (1) ES512466A0 (en)
YU (1) YU106082A (en)
ZA (1) ZA822690B (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4726895A (en) * 1986-03-28 1988-02-23 Edward Martinez Process for concentration of gold and uranium magnetically
KR101322083B1 (en) * 2007-05-30 2013-10-25 주식회사 케이씨씨 A method for eliminating iron content from pyrophyllite
CN106890623B (en) * 2017-03-09 2019-11-08 中国工程物理研究院核物理与化学研究所 A kind of extraction of uranium from seawater adsorbent and preparation method thereof having anti-microbial property

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2965440A (en) * 1957-01-11 1960-12-20 Tripp Res Corp Method of beneficiating uranium ores by forming ferromagnetic uranium values and magnetically separating same
US3394997A (en) * 1965-04-12 1968-07-30 Gen Electric Method of preparing uranium diuranate
US3676337A (en) * 1970-07-09 1972-07-11 Massachusetts Inst Technology Process for magnetic separation
GB1555670A (en) * 1977-12-12 1979-11-14 Atomic Energy Authority Uk Magnetic separation of particles from liquids in a process for reprocessing nuclear fuel

Also Published As

Publication number Publication date
EP0066419A2 (en) 1982-12-08
YU106082A (en) 1985-03-20
ES8403976A1 (en) 1984-04-01
KR900000397B1 (en) 1990-01-25
EP0066419B1 (en) 1986-09-03
ES512466A0 (en) 1984-04-01
DE3272997D1 (en) 1986-10-09
JPS5930651B2 (en) 1984-07-28
JPS57200224A (en) 1982-12-08
ZA822690B (en) 1983-06-29
EP0066419A3 (en) 1983-11-02

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