Background <p>In nuclear medicine, radiopharmaceutical drugs (RPDs) containing the technetium isotope Tc-99m are used to treat oncological diseases, such as brain, thyroid, and salivary gland cancer, as well as for diagnostic studies of the cardiovascular system. These RPDs are created using a&#xa0;molybdenum-technetium Tc-99m generator.</p> Aim <p>To determine the main parameters of complex protection for a&#xa0;designed transport container of a&#xa0;technetium generator for the production of RPDs in accordance with the GMP standard.</p> Materials and methods <p>Eighteen container material options were considered. To assess the protective characteristics of the container, we used the MicroShield v.&#xa0;8.01 software. Transport indices and categories of all container options were determined taking into account the calculated rate of equivalent doses for gamma radiation from the Mo-99/Tc-99m sorption column and the nominal source activity.</p> Results <p>We have simulated an advanced protective container for the Tc-99m generator. The best protective characteristics are noted for the option combining tungsten and lead&#xa0;2.5 and 3.5 cm thick, respectively.</p> Conclusion <p>This complex design of the protective container ensures the safe operation and transportation of the Tc-99m generator.</p>

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Justification of a protective container for a Tc-99m generator

  • N. V. Kuznetsov,
  • O. Yu. Kochnov,
  • D. V. Stepchenkov,
  • V. V. Fomichev

摘要

Background

In nuclear medicine, radiopharmaceutical drugs (RPDs) containing the technetium isotope Tc-99m are used to treat oncological diseases, such as brain, thyroid, and salivary gland cancer, as well as for diagnostic studies of the cardiovascular system. These RPDs are created using a molybdenum-technetium Tc-99m generator.

Aim

To determine the main parameters of complex protection for a designed transport container of a technetium generator for the production of RPDs in accordance with the GMP standard.

Materials and methods

Eighteen container material options were considered. To assess the protective characteristics of the container, we used the MicroShield v. 8.01 software. Transport indices and categories of all container options were determined taking into account the calculated rate of equivalent doses for gamma radiation from the Mo-99/Tc-99m sorption column and the nominal source activity.

Results

We have simulated an advanced protective container for the Tc-99m generator. The best protective characteristics are noted for the option combining tungsten and lead 2.5 and 3.5 cm thick, respectively.

Conclusion

This complex design of the protective container ensures the safe operation and transportation of the Tc-99m generator.