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Jang J, Sekimoto S, Ohtsuki T, Tatenuma K, Tsuguchi A, Uesaka M. A quantitative description of the compatibility of technetium-selective chromatographic technetium-99m separation with low specific activity molybdenum-99. J Chromatogr A 2023; 1705:464192. [PMID: 37459808 DOI: 10.1016/j.chroma.2023.464192] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/22/2023] [Revised: 06/29/2023] [Accepted: 07/01/2023] [Indexed: 08/09/2023]
Abstract
Technetium-99m generators employing a technetium-selective stationary phase are a chromatographic instrument developed for use with 99Mo having low specific activity (LSA); particularly, 99Mo produced by electron accelerators. This paper presents a mathematical description of technetium-selective chromatographic (TSC) 99mTc separation and analyzes its compatibility with LSA 99Mo. We developed a theoretical formula for TSC 99mTc separation by discretizing its pertechnetate selectivity, and validated it using an electron linear accelerator and activated carbon-based TSC (AC-TSC) 99mTc generators. We confirmed that the activity concentration of 99mTc obtained from a TSC 99mTc generator can be calculated directly from its input 99Mo activity regardless of the 99Mo specific activity. The formula corroborates that TSC 99mTc separation is compatible with LSA 99Mo, and has a practical application in estimating the number of TSC 99mTc generators required for 99mTc demand of interest.
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Affiliation(s)
- Jaewoong Jang
- Department of Bioengineering, School of Engineering, University of Tokyo, 7-3-1 Hongo, Bunkyo, Tokyo 113-8656, Japan; Isotope Science Center, University of Tokyo, 2-11-16 Yayoi, Bunkyo, Tokyo 113-0032, Japan.
| | - Shun Sekimoto
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, 2-1010 Asashironishi, Kumatori, Sennan, Osaka 590-0494 Japan
| | - Tsutomu Ohtsuki
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, 2-1010 Asashironishi, Kumatori, Sennan, Osaka 590-0494 Japan
| | | | | | - Mitsuru Uesaka
- Department of Bioengineering, School of Engineering, University of Tokyo, 7-3-1 Hongo, Bunkyo, Tokyo 113-8656, Japan; Nuclear Professional School, School of Engineering, University of Tokyo, 2-22 Shirakata-shirane, Tokai, Naka, Ibaraki 319-1188, Japan
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Zaidi JH, Wasim M, Arif M, Mushtaq A. Development of radiochemistry in Pakistan – 1960 to 2010. RADIOCHIM ACTA 2014. [DOI: 10.1524/ract.2012.1952] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
Abstract
Abstract
With the inception of Pakistan Atomic Energy Commission (PAEC) in 1956, peaceful uses of atomic energy commenced for the benefit of scientific community as well as masses of Pakistan. Radiochemistry played a vital role right from the beginning. The research and development in this field accelerated soon after the criticality of the first research reactor named as Pakistan Research Reactor (PARR- 1) at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), Islamabad. The first radioisotope produced at PARR-1 for application in nuclear medicine was 131I. Later on, many other radioisotopes were prepared and radiopharmaceuticals were synthesised for their use in industry and hospitals. Besides providing pure radioactive tracers for nuclear medicine, radiochemistry also enhanced the detection limit of impurities at all stages of nuclear fuel cycle for power generation. In 1983, research in the field of nuclear data measurement began. The main aim was to identify suitable conditions for the production of radionuclides for cancer diagnostics, treatment and therapy. With the establishment of a second research reactor (PARR-2) at PINSTECH, research in neutron activation analysis, radioisotope production and separation studies gained more momentum and many research articles were published. Solvent extraction, adsorption and ion-exchange were the main routes of separation in those studies. Separation of heavy metals and treatment of waste generated in a nuclear power plant are other important aspects related to environmental restoration and nuclear waste management, where radiochemistry is required. In future, work in radiochemistry will be continued on similar lines to develop novel radiopharmaceuticals, identify indigenous schemes for nuclear waste management and work out intelligent procedures for material characterization for benefit to mankind, especially the people of Pakistan.
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Affiliation(s)
- J. H. Zaidi
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
| | - M. Wasim
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
| | - M. Arif
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
| | - A. Mushtaq
- Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad, Pakistan
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Chakravarty R, Sarkar S, Venkatesh M, Dash A. An electrochemical procedure to concentrate 99mTc availed from a zirconium [99Mo] molybdate gel generator. Appl Radiat Isot 2012; 70:375-9. [DOI: 10.1016/j.apradiso.2011.09.024] [Citation(s) in RCA: 11] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 06/23/2011] [Accepted: 09/20/2011] [Indexed: 11/16/2022]
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Evaluation of highly loaded low specific activity 99Mo on alumina column as 99mTc generator. J Radioanal Nucl Chem 2010. [DOI: 10.1007/s10967-010-0490-z] [Citation(s) in RCA: 12] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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