GB1389905A - Production of high purity fission product molybdenum-99 - Google Patents

Production of high purity fission product molybdenum-99

Info

Publication number
GB1389905A
GB1389905A GB3050772A GB3050772A GB1389905A GB 1389905 A GB1389905 A GB 1389905A GB 3050772 A GB3050772 A GB 3050772A GB 3050772 A GB3050772 A GB 3050772A GB 1389905 A GB1389905 A GB 1389905A
Authority
GB
United Kingdom
Prior art keywords
solution
june
dissolving
contacting
precipitate
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
GB3050772A
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.)
Union Carbide Corp
Original Assignee
Union Carbide Corp
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 Union Carbide Corp filed Critical Union Carbide Corp
Publication of GB1389905A publication Critical patent/GB1389905A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
    • G21G1/06—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation
    • G21G1/08—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation accompanied by nuclear fission
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G39/00—Compounds of molybdenum
    • C01G39/003—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • Inorganic Chemistry (AREA)
  • General Chemical & Material Sciences (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

1389905 Separating radio-isotopes UNION CARBIDE CORP 29 June 1972 [30 June 1971] 30507/72 Heading G6R Radioactive molybdenum-99 is prepared by irradiating a uranium material to produce nuclear fission therein, dissolving in aqueous inorganic acid, contacting the solution with alpha-benzoin oxime to precipitate Mo-99, dissolving the separated precipitate in aqueous alkali solution, contacting the solution with silver coated charcoal, an inorganic ion adsorbent, and/or activated carbon in order to remove impurities, and then recovering the Mo-99. The inorganic acid used may be sulphuric acid mixed with nitric acid or hydrogen peroxide. Before precipitation of the Mo, sodium sulphite may be added as a reducing agent, and a ruthenium salt or an iodide to reduce the impurity level. For further purification the alkaline solution is acidified and the Mo again precipitated. Suitable ion adsorbents are silica gel, ZrO 2 , Al 2 O 3 , TiO 2 , iron oxide, aluminium phosphate and aluminium silicates. In an example the fissile material is coated on to the inside surface of a hollow stainless steel cylindrical container and after irradiation this container is used for part of the separation process. The separated Mo-99 is supported on alumina, the daughter product technetium- 99m being eluted for use in medical diagnosis.
GB3050772A 1971-06-30 1972-06-29 Production of high purity fission product molybdenum-99 Expired GB1389905A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US00158396A US3799883A (en) 1971-06-30 1971-06-30 Production of high purity fission product molybdenum-99

Publications (1)

Publication Number Publication Date
GB1389905A true GB1389905A (en) 1975-04-09

Family

ID=22567913

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3050772A Expired GB1389905A (en) 1971-06-30 1972-06-29 Production of high purity fission product molybdenum-99

Country Status (9)

Country Link
US (1) US3799883A (en)
JP (1) JPS517800B1 (en)
BE (1) BE785637A (en)
CA (1) CA969373A (en)
DE (1) DE2231976C3 (en)
FR (1) FR2157781B1 (en)
GB (1) GB1389905A (en)
IL (1) IL39793A (en)
NL (1) NL172495C (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4659477A (en) * 1982-08-16 1987-04-21 Pedro B. Macedo Fixation of anionic materials with a complexing agent
RU2489501C1 (en) * 2011-12-01 2013-08-10 Общество с ограниченной ответственностью "Прайм-Инвест" COMPOSITION OF EXTRACTION-CHROMATOGRAPHIC MATERIAL FOR SELECTIVE EXTRACTION OF Mo-99 FROM IRRADIATED URANIUM FUEL

Families Citing this family (42)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4010109A (en) * 1973-07-02 1977-03-01 Kurt Sauerwein Device for marking fluent materials
GB1531985A (en) * 1975-03-06 1978-11-15 Radiochemical Centre Ltd Technetium-99m
DE2610948C3 (en) * 1976-03-16 1980-01-10 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the extraction of molybdenum -99 from a matrix containing fissile substances and fission products irradiated with neutrons
DE2610947C3 (en) * 1976-03-16 1980-01-10 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the extraction of molybdenum-99 from a matrix containing fissile substances and fission products irradiated with neutrons
US4199551A (en) * 1978-01-13 1980-04-22 Amax Inc. Recovery of molybdenum and uranium from activated charcoal containing molybdenum and residual uranium
JPS5525844U (en) * 1978-08-10 1980-02-19
DK151919C (en) * 1979-06-28 1988-08-15 Radiometer As PROCEDURE, REFERENCE LIQUID, AND REFERENCE LIQUID SYSTEM FOR SIMILAR CALIBRATION AND / OR QUALITY CONTROL OF CALCIUM SENSITIVE ELECTRODE AND PH ELECTRODE
FR2531060B1 (en) * 1982-07-28 1986-07-04 Cogema PROCESS FOR RECOVERING MOLYBDENE FROM ACTIVE CARBON FROM AN ACID URANIFEROUS SOLUTION CONTAINING MORE MOLYBDENE THAN URANIUM
JPS59114881U (en) * 1983-01-24 1984-08-03 株式会社貝印刃物開発センター pod support structure
FR2575585B1 (en) * 1984-12-28 1987-01-30 Commissariat Energie Atomique PROCESS FOR RECOVERY OF MOLYBDENE-99 FROM AN IRRADIATED URANIUM ALLOY TARGET
FR2583403B1 (en) * 1985-06-13 1988-11-10 Pechiney Uranium PROCESS FOR THE SEPARATION, BY PRECIPITATION, OF MOLYBDENE CONTAINED IN SULFURIC OR NITRIC SOLUTIONS OF URANIUM.
DE3616391A1 (en) * 1986-05-15 1987-11-19 Kernforschungsz Karlsruhe METHOD FOR THE FINE CLEANING OF SPLIT MOLYBDA
US4839133A (en) * 1987-10-26 1989-06-13 The United States Of America As Represented By The Department Of Energy Target and method for the production of fission product molybdenum-99
US5846455A (en) * 1995-12-11 1998-12-08 Institut National Des Radio Elements Method of stabilizing an aqueous solution of 99 Mo molybdate
US5802438A (en) * 1997-02-19 1998-09-01 Lockheed Martin Idaho Technologies Company Method for generating a crystalline 99 MoO3 product and the isolation 99m Tc compositions therefrom
US5802439A (en) * 1997-02-19 1998-09-01 Lockheed Martin Idaho Technologies Company Method for the production of 99m Tc compositions from 99 Mo-containing materials
IT1316223B1 (en) * 2000-09-28 2003-04-03 Carlo Rubbia METHOD AND DEVICE FOR HEATING GAS FROM A THIN NUCLEAR DUCTILE FUEL LAYER AND SPATIAL PROPULSER USING SUCH METHOD.
US8666015B2 (en) 2001-05-08 2014-03-04 The Curators Of The University Of Missouri Method and apparatus for generating thermal neutrons using an electron accelerator
US20060023829A1 (en) * 2004-08-02 2006-02-02 Battelle Memorial Institute Medical radioisotopes and methods for producing the same
US8497683B2 (en) * 2006-10-03 2013-07-30 Invensys Systems, Inc. Spectroscopic sample analyzer and sample handling system
KR101353730B1 (en) * 2008-02-05 2014-01-20 더 큐레이터스 오브 더 유니버시티 오브 미주리 Radioisotope production and treatment of solution of target material
RU2494484C2 (en) * 2008-05-02 2013-09-27 Шайн Медикал Текнолоджис, Инк. Production device and method of medical isotopes
US20100169134A1 (en) * 2008-12-31 2010-07-01 Microsoft Corporation Fostering enterprise relationships
US9691511B1 (en) * 2009-11-09 2017-06-27 Sandia Corporation Target-fueled nuclear reactor for medical isotope production
WO2012003009A2 (en) 2010-01-28 2012-01-05 Shine Medical Technologies, Inc. Segmented reaction chamber for radioisotope production
JP5974240B2 (en) * 2010-02-19 2016-08-23 ビーダブリューエクスティー・テクニカル・サービシーズ・グループ・インコーポレイテッドＢｗｘｔ Ｔｅｃｈｎｉｃａｌ Ｓｅｒｖｉｃｅｓ Ｇｒｏｕｐ，Ｉｎｃ． Method for extracting molybdenum
US9240253B2 (en) * 2010-04-07 2016-01-19 Ge-Hitachi Nuclear Energy Americas Llc Column geometry to maximize elution efficiencies for molybdenum-99
EP2398023A1 (en) 2010-06-21 2011-12-21 The European Union, represented by the European Commission Production of molybdenum-99
GB201013142D0 (en) 2010-08-04 2010-09-22 Mallinckrodt Inc Purification process
DE102011002265B4 (en) * 2011-04-26 2012-12-06 Technische Universität München Process for the preparation of starting material for a technetium generator
US10734126B2 (en) * 2011-04-28 2020-08-04 SHINE Medical Technologies, LLC Methods of separating medical isotopes from uranium solutions
GB201112051D0 (en) * 2011-07-13 2011-08-31 Mallinckrodt Llc Process
JP5888781B2 (en) * 2011-11-14 2016-03-22 国立研究開発法人日本原子力研究開発機構 Method for producing radioactive molybdenum
KR102172861B1 (en) 2012-04-05 2020-11-02 샤인 메디컬 테크놀로지스, 인크. Aqueous assembly and control method
US9330800B2 (en) * 2012-12-03 2016-05-03 Wisconsin Alumni Research Foundation Dry phase reactor for generating medical isotopes
US9997267B2 (en) 2013-02-13 2018-06-12 Battelle Memorial Institute Nuclear reactor target assemblies, nuclear reactor configurations, and methods for producing isotopes, modifying materials within target material, and/or characterizing material within a target material
US9793023B2 (en) 2013-09-26 2017-10-17 Los Alamos National Security, Llc Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target
US9842664B2 (en) 2013-09-26 2017-12-12 Los Alamos National Security, Llc Recovering and recycling uranium used for production of molybdenum-99
CN109285616B (en) * 2018-11-16 2020-08-21 中国原子能科学研究院 From235Extraction from U fission products99Device for extracting Mo and extracting Mo by using device99Method for Mo
US12040102B2 (en) * 2020-04-16 2024-07-16 Uchicago Argonne, Llc Technetium-99M generator for enriched molybdenum
US20210407699A1 (en) * 2020-06-30 2021-12-30 Uchicago Argonne, Llc System and method for producing molybdenum 99
EP3985686B1 (en) 2020-10-14 2022-11-30 Narodowe Centrum Badan Jadrowych Method of preparation of the uranium target for the production of molybdenum, molybdenum production process and the uranium target for the production of molybdenum

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4659477A (en) * 1982-08-16 1987-04-21 Pedro B. Macedo Fixation of anionic materials with a complexing agent
RU2489501C1 (en) * 2011-12-01 2013-08-10 Общество с ограниченной ответственностью "Прайм-Инвест" COMPOSITION OF EXTRACTION-CHROMATOGRAPHIC MATERIAL FOR SELECTIVE EXTRACTION OF Mo-99 FROM IRRADIATED URANIUM FUEL

Also Published As

Publication number Publication date
NL7209050A (en) 1973-01-03
BE785637A (en) 1972-12-29
DE2231976A1 (en) 1973-01-11
JPS517800B1 (en) 1976-03-11
IL39793A (en) 1976-01-30
DE2231976C3 (en) 1980-03-27
FR2157781B1 (en) 1976-10-29
DE2231976B2 (en) 1979-07-19
NL172495C (en) 1983-09-01
NL172495B (en) 1983-04-05
FR2157781A1 (en) 1973-06-08
US3799883A (en) 1974-03-26
CA969373A (en) 1975-06-17
IL39793A0 (en) 1972-09-28

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PE20 Patent expired after termination of 20 years