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<p>This work developed a method to determine the contamination rates of iodine-126 (<sup>126</sup>I) in the sodium iodide (NaI) solution used in the production of iodine-125 (<sup>125</sup>I) seeds for brachytherapy. The production of <sup>125</sup>I is carried out at the IEA-R1 Reactor of the Nuclear and Energy Research Institute (IPEN-CNEN/SP) by irradiation with natural xenon. For the radionuclide analysis, a High-Purity Germanium (HPGe) radiation detector (ORTEC model GEM-C5970-B, coaxial detection system and beryllium window, nominal efficiency of 43% at 1333&#xa0;keV of cobalt-60) was used, in which the activity of <sup>125</sup>I was determined by the sum-peak method and the activity of <sup>126</sup>I by an efficiency curve using a <sup>166</sup><sup>m</sup>Ho calibration source (A = (1832 ± 2) Bq, T<sub>1/2</sub> = 1.20 × 10<sup>3</sup>&#xa0;years and reference date: Feb 23rd 2024). The results demonstrated the predictions of <sup>125</sup>I production in the IEA-R1 Reactor with <sup>126</sup>I contamination levels below 0.005%, meeting the production requirements for clinical use.</p>

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Analysis of iodine-126 contamination in the production of iodine-125 at the IEA-R1 reactor for brachytherapy applications

  • 期刊论文

  • 出版模式：

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  • 发表日期：

    2026年3月5日

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  • Ilca Marli Moitinho Amaral Medeiros,
  • João Augusto Moura,
  • José Agostinho Gonçalves de Medeiros,
  • Ana Catarina Souza Silva Koka,
  • Lucas Verdi Angelocci,
  • Maria Elisa Chuery Martins Rostelato,
  • Carlos Alberto Zeituni

摘要

This work developed a method to determine the contamination rates of iodine-126 (126I) in the sodium iodide (NaI) solution used in the production of iodine-125 (125I) seeds for brachytherapy. The production of 125I is carried out at the IEA-R1 Reactor of the Nuclear and Energy Research Institute (IPEN-CNEN/SP) by irradiation with natural xenon. For the radionuclide analysis, a High-Purity Germanium (HPGe) radiation detector (ORTEC model GEM-C5970-B, coaxial detection system and beryllium window, nominal efficiency of 43% at 1333 keV of cobalt-60) was used, in which the activity of 125I was determined by the sum-peak method and the activity of 126I by an efficiency curve using a 166mHo calibration source (A = (1832 ± 2) Bq, T1/2 = 1.20 × 103 years and reference date: Feb 23rd 2024). The results demonstrated the predictions of 125I production in the IEA-R1 Reactor with 126I contamination levels below 0.005%, meeting the production requirements for clinical use.