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Selective separation of uranium, zirconium and iodine from various fission products by 1-butyl-3-methylimidazolium bis(trifluoromethanesulfonyl)imide and phosphoramide-functionalized ionic liquid. J Radioanal Nucl Chem 2022. [DOI: 10.1007/s10967-022-08396-w] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Selective adsorption of molybdenum ions on ionic liquid-loaded resin containing 1-butyl-3-methylimidazolium(2,4,6-trimethyl)benzodithioate. J Radioanal Nucl Chem 2021. [DOI: 10.1007/s10967-021-07970-y] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Bettinardi DJ, Brown MA, Paulenova A, Tsai Y, Tkac P. Separation and determination of ultratrace rhenium quantities in molybdenum matrix. SEP SCI TECHNOL 2020. [DOI: 10.1080/01496395.2020.1849304] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Submit a Manuscript] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
Affiliation(s)
- David J. Bettinardi
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, IL, USA
- School of Nuclear Science and Engineering, Oregon State University, Corvallis, OR, USA
| | - M. Alex Brown
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, IL, USA
| | - Alena Paulenova
- School of Nuclear Science and Engineering, Oregon State University, Corvallis, OR, USA
| | - Yifen Tsai
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, IL, USA
| | - Peter Tkac
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, IL, USA
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Stepinski DC, Youker AJ, Chemerisov SD, Tkac P, Rotsch DA, Krebs JF, Vandegrift GF. Development of Mo recovery and concentration column processes for production of 99Mo from accelerator-driven irradiation of aqueous uranyl-sulfate solution. SEP SCI TECHNOL 2020. [DOI: 10.1080/01496395.2019.1591448] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Submit a Manuscript] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Affiliation(s)
| | - Amanda J. Youker
- Nuclear Engineering Division, Argonne National Laboratory, Illinois, US
| | | | - Peter Tkac
- Nuclear Engineering Division, Argonne National Laboratory, Illinois, US
| | - David A. Rotsch
- Nuclear Engineering Division, Argonne National Laboratory, Illinois, US
| | - John F. Krebs
- Nuclear Engineering Division, Argonne National Laboratory, Illinois, US
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Stepinski DC, Youker AJ, Krahn EO, Vandegrift GF, Chung PL, Wang NHL. Design of a Fission 99Mo Recovery Process and Implications toward Mo Adsorption Mechanism on Titania and Alumina Sorbents. Ind Eng Chem Res 2017. [DOI: 10.1021/acs.iecr.6b04667] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
Affiliation(s)
- Dominique C. Stepinski
- Nuclear
Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, United States
| | - Amanda J. Youker
- Nuclear
Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, United States
| | - Elizabeth O. Krahn
- Nuclear
Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, United States
| | - George F. Vandegrift
- Nuclear
Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, United States
| | - Pei-Lun Chung
- School
of Chemical Engineering, Purdue University, West Lafayette, Indiana 47907, United States
| | - Nien-Hwa Linda Wang
- School
of Chemical Engineering, Purdue University, West Lafayette, Indiana 47907, United States
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Separation of tungsten from LEU fission-produced 99Mo solution to improve technological performance in both the processes of 99Mo and 99mTc generator production. J Radioanal Nucl Chem 2015. [DOI: 10.1007/s10967-014-3426-1] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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van der Walt T, Coetzee PP. The isolation of99Mo from fission material for use in the99Mo/99mTc generator for medical use. RADIOCHIM ACTA 2009. [DOI: 10.1524/ract.92.4.251.35589] [Citation(s) in RCA: 14] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
Abstract
AbstractMolybdenum-99 is an important radionuclide which is used in nuclear medicine and a new method is presented for the isolation and purification of99Mo from fission material. The method was developed to suit the needs of the Nuclear Energy Corporation of South Africa (NECSA) and also because most other methods had been patented and could therefore not be used at NECSA. A uranium-aluminium alloy, cladded in aluminium, served as a target and the target was irradiated in a nuclear reactor for several days. After a cooling period, in order to let the short-lived radionuclides decay, the target material was dissolved in a sodium hydroxide solution. The radioactive krypton and xenon gases were collected on activated carbon and stored until both gases had decayed. Aluminium,99Mo,131I and the radionuclides of alkali-soluble elements in the sodium hydroxide solution were separated from the uranium and radionuclides of the alkaline-insoluble elements by filtration. The radionuclides of molybdenum and iodine were separated by anion exchange chromatography, in alkaline medium, from the bulk aluminium and radionuclides of other elements, such as barium, strontium and tellurium.99Mo was selectively eluted with a slightly alkaline lithium sulphate solution, leaving the iodine radionuclides on the resin. The99Mo eluant was acidified with oxalic acid and nitric acid and99Mo separated from the remaining aluminium and other radionuclides by anion exchange chromatography, in acid medium. After elution of99Mo, again with a slightly alkaline lithium sulphate solution, the eluant was acidified with nitric acid,99Mo concentrated on a chelating resin column and finally eluted with ammonia and evaporated to obtain99MoO3which was then dissolved in diluted sodium hydroxide solution. The purity of the final product was within the specifications of the British and European Pharmacopoiea and no further purification steps, such as sublimation, were required.
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