Preparation of 113mIn-generator from enriched 112Sn metal

Lin, Tsing-Ko; Tsai, Zei-Tsan; Luan, Chau-sung

doi:10.1016/0020-708x(82)90094-1

Cited by 14 publications

(2 citation statements)

References 9 publications

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“…The 113 Sn parent is readily reactor produced, 72 has a half-life of 118 days and decays by electron capture. The 113 Sn/ 113m In generator has the following advantages.…”

Section: Potentially Useful Irg Systemsmentioning

confidence: 99%

Industrial radionuclide generators: a potential step towards accelerating radiotracer investigations in industry

2013

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The novel use of industrial radionuclide generators (IRG) ensures onsite availability of short-lived radionuclides and is expected to contribute significantly to industrial radiotracer investigations. While IRG technology is in its infancy, the use of generator-derived radioisotopes is expected to have broad potential impact on industrial radiotracer investigations. The optimal combination of suitable IRGs and appropriate radiotracer agents will form the basis of such industrial radiotracer investigations. Development of IRGs customized for specific applications is currently under development and the utility of such systems is expected to pave the way for a variety of industry related applications in the areas of residence time distribution (RTD) study, flow rate measurement, leak detection, etc. In this review, we discuss the principles of radionuclide generators, assess major parent/daughter pairs of interest for IRG, and identify the expected utility of potentially useful IRGs. Availability of the parent radionuclides required for IRG fabrication is an important criterion and hence their production is also reviewed. This overview outlines a critical assessment of recent developments, the contemporary status, and key challenges and apertures to the near future. Increase in the knowledge and use of IRGs utilizing available resources will encourage expanded use of these systems for expected future industrial radiotracer studies.Prof. M. R. A.Pillai, PhD, DSc retired as Head, Radiopharmaceuticals Division, BARC in 2013. He worked at the University of Missouri-Columbia as postdoctoral research associate (1987-89) and as visiting professor (1994). He served the IAEA (2003IAEA ( -2010 as a Technical Officer, in which capacity he directed projects on isotopes and radiopharmaceuticals involving 40 countries as well published 14 IAEA documents. He is an Associate Editor of Cancer Biotherapy and Radiopharmaceuticals and is a member of the Editorial Boards of Current Medicinal Chemistry, Current Radiopharmaceuticals and the American Journal of Nuclear medicine and Molecular Imaging. He has authored three books, 130 papers including 10 review articles, and holds two US patents.

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“…The 113 Sn parent is readily reactor produced, 72 has a half-life of 118 days and decays by electron capture. The 113 Sn/ 113m In generator has the following advantages.…”

Section: Potentially Useful Irg Systemsmentioning

confidence: 99%

Industrial radionuclide generators: a potential step towards accelerating radiotracer investigations in industry

2013

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“…18-22 99m Tc is usually eluted from these columns using 0.9% NaCl. Subramanian and McAfee, 23 and Lin et al 24 studied separately the use of hydrous zirconium oxide (HZO) column for adsorption of 113 Sn from 0.3-0.5 M and 0.2 M HCl, respectively, and elution of 113m In with 0.1 M HNO 3 (or 0.1 M HCl) and 0.05 M HCl, respectively. Arino and Kramer 25 studied the chemical sorption of 113 Sn(IV) separately on HZO and silica gel by heating in the presence of bromine water and 0.4 M HCl.…”

Section: Introduction 99mmentioning

confidence: 99%

99Mo/99mTc-113Sn/113mIn Dual Radioisotope Generator Based on 6-Tungstocerate(IV) Column Matrix

Mostafa

El‐Sadek

El-Said

et al. 2009

Journal of Nuclear and Radiochemical Sciences

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Elutions of 99m Tc and 113m In have been performed subsequently with 10 mL of 0.9% NaCl solution and 10 mL of 0.1 M HCl solution, respectively, from 6-tungstocerate(IV) chromatographic column loaded with 0.54 MBq 99 Mo and 0.45 MBq 113 Sn, using alumina-column filter in the case of 99m Tc. Radionuclidic purity of both eluates was ≥ 99.99%. Elution yields of 72.5±5.8% and 62.2±3.7%, and radiochemical purities of 96.9±1.0% (as 99m TcO 4-) and 88.4±2.5% (as 113m In 3+) have been obtained for 99m Tc and 113m In, respectively. Al and W impurities in the 99m Tc and 113m In eluates, respectively, were found to be within the accepted limits, whereas no Ce impurities were detected in both eluates. Also trials have been carried out on a similar system to obtain mixed 99m Tc-113m In eluates from 6tungstocerate column with different 99m Tc/ 113m In ratios using 0.9% NaCl-HCl eluents of different pH values. To separate 99m Tc and 113m In from each other, these mixed eluates were passed through a column of hydrous zirconium oxide which was then eluted with 10 mL of 0.9% NaCl solution and 15 mL of 0.1 M HCl solution, respectively. No W, Ce, or Zr impurities were detected in the 99m Tc and 113m In eluates obtained in these trials.

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Adsorption of several tracer cations and separation of234Th from238U and113mIn from113Sn on tin dioxide

Bhattacharyya

Dutta

1990

Journal of Radioanalytical and Nuclear Chemistry, Articles

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Preparation of 113mIn-generator from enriched 112Sn metal

Cited by 14 publications

References 9 publications

Industrial radionuclide generators: a potential step towards accelerating radiotracer investigations in industry

Industrial radionuclide generators: a potential step towards accelerating radiotracer investigations in industry

<sup>99</sup>Mo/<sup>99m</sup>Tc-<sup>113</sup>Sn/<sup>113m</sup>In Dual Radioisotope Generator Based on 6-Tungstocerate(IV) Column Matrix

Adsorption of several tracer cations and separation of234Th from238U and113mIn from113Sn on tin dioxide

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