Geant4/GATE Monte Carlo Code for Internal Dosimetry Using Voxelized Phantom
- 21 Downloads
It is of great interest to estimate absorbed doses in organs before radiation therapy, especially in nuclear medicine field. In this regard, the internal dose distribution is required. According to the MIRD formalism, Specific Absorbed Fraction (SAF) is an essential parameter for internal dosimetry. In the present work, SAF values for the voxelized phantom (Golem) of the GSF-National Research Center for Environment and Health were calculated using Geant4/GATE with Standard packages and compared with GSF Monte Carlo reference data. Photon irradiations of 30, 100 keV and 1 MeV energy were simulated in eleven different sources and target organs: liver, kidneys, lungs, brain, pancreas, spleen, colon, Red bone marrow (RBM), stomach, thyroid and adrenals. The SAF for self-absorption and for cross-irradiation to other organs were calculated and compared with literature. The results agree with published data, with an average relative difference less than 3%, for the self-absorption of 100 keV and 1 MeV photon energies. The agreement of Geant4/GATE and GSF code might depend on the distance between target and source, the target mass and the photons energy. Generally, the present results indicate that GATE might be used with gamma emitters for internal dosimetry in regard to our prospective works.
Keywordsinternal dosimetry Geant4/GATE voxelized phantoms specific absorbed fraction
Unable to display preview. Download preview PDF.
- 1.D. L. Bailey, A. van Aswegen, et al., Nuclear Medicine Physics: A Handbook for Teachers and Students (International Atomic Energy Agency, Vienna, 2014).Google Scholar
- 2.International Commission on Radiological Protection, Radiation Dose to Patients from Radiopharmaceuticals (Pergamon, Oxford, UK, 1987).Google Scholar
- 3.W. S. Snyder et al., “Estimates of absorbed fractions for monoenergetic photon sources uniformly distributed in various organs of a heterogeneous phantom,” J. Nucl. Med. 10, 7–52 (1969).Google Scholar
- 8.Geant4 Collaboration. www.geant4.cern.ch. 2010.Google Scholar
- 14.M. Zankl et al., “Assessment of body doses from photon exposures using human voxel models,” (in Proc. 10th Int. Congress of the International Radiation Protection Association, Hiroshima, Japan, 2000).Google Scholar
- 15.D. Sarrut, M. Bardiès, N. Boussion, N. Freud, S. Jan, J.-M. Létang, et al., “A review of the use and potential of the GATE Monte Carlo simulation code for radiation therapy and dosimetry applications,” Med. Phys. 41, (064301), (2014).Google Scholar
- 16.R. Veit et al., Tomographic Anthropomorphic Models, Part I: Construction Technique and Description of Models of an 8 Week Old Baby and a 7 Year Old Child (Gesellschaft für Strahlen- und Umweltforschung, München, 1989).Google Scholar