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Internal dosimetry with the Monte Carlo code GATE: validation using the ICRP/ICRU female reference computational

Daphnée Villoing1, Sara Marcatili, Marie-Paule Garcia

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Summary

This study validates the GATE simulation software for clinical nuclear medicine dosimetry. GATE accurately calculates absorbed doses, showing less than 10% difference compared to MCNPX, making it reliable for radiopharmaceutical dosimetry.

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Area of Science:

  • Medical Physics
  • Nuclear Medicine
  • Computational Dosimetry

Background:

  • Accurate absorbed dose calculations are crucial for nuclear medicine dosimetry.
  • Monte Carlo simulations are widely used for these calculations.
  • Validation of simulation tools is essential for clinical application.

Purpose of the Study:

  • To validate the GATE (version 6.2) simulation toolkit for clinical-scale absorbed dose calculations in nuclear medicine.
  • To compare GATE-derived dosimetric parameters with those from MCNPX (version 2.7.a).
  • To assess the suitability of GATE for radiopharmaceutical dosimetry.

Main Methods:

  • Used GATE and MCNPX to calculate dosimetric parameters (absorbed fractions, specific absorbed fractions, S-values).
  • Employed the ICRP 110 female computational model.
  • Investigated monoenergetic photons/electrons (50 keV–2 MeV) and isotopes F-18, Lu-177, I-131, Y-90.
  • Generated data for 144 source/target configurations across 12 regions of interest.

Main Results:

  • Relative differences between GATE and MCNPX were consistently below 10%, often less than 5%.
  • This agreement was observed for self-irradiation and cross-irradiation scenarios.
  • Dosimetric results from GATE were provided as supplemental data.

Conclusions:

  • GATE (version 6.2) is validated for clinical-scale absorbed dose calculations in nuclear medicine.
  • GATE is a safe and viable tool for Monte Carlo modeling in radiopharmaceutical dosimetry, encompassing both imaging and dose calculation.
  • The findings support the use of GATE in clinical nuclear medicine settings.