A comparison between GATE4 results and MCNP4B published data for internal radiation dosimetry

Parach, Ali Asghar; Rajabi, Hamid

doi:10.3413/nukmed-0363-10-10

Cited by 10 publications

(5 citation statements)

References 36 publications

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“…The doses calculated using the voxelized MC simulation are consistent with OLINDA/EXM to within 5%. The agreement between this simulation and OLINDA/EXM is consistent with other comparisons between different Monte Carlo codes for dosimetry [21][22][23].…”

Section: Monte Carlo Dose Calculationssupporting

confidence: 88%

Improving molecular radiotherapy dosimetry using anthropomorphic calibration

et al. 2019

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The optimised delivery of Molecular Radiotherapy requires individualised calculation of absorbed dose to both targeted lesions and neighbouring healthy tissue. To achieve this, accurate quantification of the activity distribution in the patient by external detection is vital. Methods: This work extends specific anatomy-related calibration to true organ shapes. A set of patient-specific 3D printed organ inserts based on a diagnostic CT scan was produced, comprising the liver, spleen and both kidneys. The inserts were used to calculate patient-specific calibration factors for 177 Lu. These calibration factors were compared with previously reported calibration factors for corresponding organ models based on the Cristy and Eckerman phantom series and for a comparably sized sphere. Monte Carlo calculations of the patientspecific radiation dose were performed for comparison with current clinical dosimetry methods for these data. Results: Patient-specific calibration factors are shown to be dependent on the volume, shape and position of the organ containing activity with a corresponding impact on the calculation of the dose to the patient. The impact of organ morphology on calculated dose is reduced when the dominant contributor to dose is beta particles. This is due to the small range of beta particles in tissue. Overestimations of recovered activity and hence dose of up to 135% are observed. Conclusion: For accurate quantification to be performed calibration factors accounting for organ size, shape and position must be used. Such quantification is vital if accurate, patient-specific dosimetry is to be achieved.

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Section: Monte Carlo Dose Calculationssupporting

confidence: 88%

Improving molecular radiotherapy dosimetry using anthropomorphic calibration

et al. 2019

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“…We inspected the consistency and agreement between the results derived from Penelope, Livermore and Geant4-standard physics models, as well as MIRD S-values, and the corresponding results obtained with Geant4-DNA physics. Pearson's product-moment coefficient was calculated so as to examine the linear relationship, and the Bland-Altman plot to verify the agreements between two series of data (Parach and Rajabi 2011). We calculated the relative difference between the two series of data (RD%) as follows: where S test represents the S-values calculated using the Penelope, Livermore and Geant4standard physics models and also the published MIRD values.…”

Section: Discussionmentioning

confidence: 99%

A comparison between track-structure, condensed-history Monte Carlo simulations and MIRD cellularS-values

2017

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The S-value is a standard measure in cellular dosimetry. S-values are calculated by applying analytical methods or by Monte Carlo simulation. In Monte Carlo simulation, particles are either tracked individually event-by-event or close events are condensed and processed collectively in different steps. Both of these methods have been employed for estimation of cellular S-values, but there is no consistency between the published results. In the present paper, we used the Geant4-DNA track-structure physics model as the reference to estimate the cellular S-values. We compared the results with the corresponding values obtained from the following three condensed-history physics models of Geant4: Penelope, Livermore and standard. The geometry and source were exactly the same in all the simulations. We utilized mono-energetic electrons with an initial kinetic energy in the range 1-700 keV as the source of radiation. We also compared our results with the MIRD S-values. We first drew an overall comparison between different data series and then compared the dependence of results on the energy of particles and the size of scoring compartments. The overall comparison indicated a very good linear correlation (R > 91%) and small bias (3%) between the results of the track-structure model and the condensed-history physics model. The bias between MIRD and the results of Monte Carlo track-structure simulation was considerable (-8%). However, the point-by-point comparison revealed differences of up to 28% between the condensed-history and the track-structure MC codes for self-absorption S-values in the 10-50 keV energy range. For the cross-absorption S-values, the difference was up to 34%. In this energy range, the difference between the MIRD S-values and the Geant4-DNA results was up to 68%. Our findings suggest that the consistency/inconsistency of the results obtained with different MC simulations depends on the size of the scoring volumes, the energy of the particles, the step-size in electron tracking and the energy cutoff used in the MC codes.

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“…Several studies have assessed the applicability of the GATE Monte Carlo package for internal dosimetry of radionuclides and related applications [3,4,20,21]. A brief summary of these studies can be found in a published review by Sarrut et al [22].…”

Section: Introductionmentioning

confidence: 98%

“…Each organ in the Zubal phantom has a unique code that identifies its voxels. This phantom has previously been used for internal dosimetry calculations with GATE/Geant4 Monte Carlo package and verified with MCNP4C data [3,4]. Otoko [5], ADELAIDE [6] and Golem [7] are similar examples of computational human models that have been constructed from CT scans of actual patients.…”

Section: Introductionmentioning

confidence: 99%

Monte Carlo and experimental internal radionuclide dosimetry in RANDO head phantom

Asl

Nasseri

Parach

et al. 2015

Australas Phys Eng Sci Med

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Monte Carlo techniques are widely employed in internal dosimetry to obtain better estimates of absorbed dose distributions from irradiation sources in medicine. Accurate 3D absorbed dosimetry would be useful for risk assessment of inducing deterministic and stochastic biological effects for both therapeutic and diagnostic radiopharmaceuticals in nuclear medicine. The goal of this study was to experimentally evaluate the use of Geant4 application for tomographic emission (GATE) Monte Carlo package for 3D internal dosimetry using the head portion of the RANDO phantom. GATE package (version 6.1) was used to create a voxel model of a human head phantom from computed tomography (CT) images. Matrix dimensions consisted of 319 × 216 × 30 voxels (0.7871 × 0.7871 × 5 mm(3)). Measurements were made using thermoluminescent dosimeters (TLD-100). One rod-shaped source with 94 MBq activity of (99m)Tc was positioned in the brain tissue of the posterior part of the human head phantom in slice number 2. The results of the simulation were compared with measured mean absorbed dose per cumulative activity (S value). Absorbed dose was also calculated for each slice of the digital model of the head phantom and dose volume histograms (DVHs) were computed to analyze the absolute and relative doses in each slice from the simulation data. The S-values calculated by GATE and TLD methods showed a significant correlation (correlation coefficient, r(2) ≥ 0.99, p < 0.05) with each other. The maximum relative percentage differences were ≤14% for most cases. DVHs demonstrated dose decrease along the direction of movement toward the lower slices of the head phantom. Based on the results obtained from GATE Monte Carlopackage it can be deduced that a complete dosimetry simulation study, from imaging to absorbed dose map calculation, is possible to execute in a single framework.

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A comparison between GATE4 results and MCNP4B published data for internal radiation dosimetry

Abstract: Despite of differences between the GATE4 and MCNP4B, the results can be considered ensuring. This may be considered as validation of GATE/GEANT as a proprietary code in nuclear medicine for radionuclide dosimetry applications.

Cited by 10 publications

References 36 publications

Improving molecular radiotherapy dosimetry using anthropomorphic calibration

Improving molecular radiotherapy dosimetry using anthropomorphic calibration

A comparison between track-structure, condensed-history Monte Carlo simulations and MIRD cellularS-values

Monte Carlo and experimental internal radionuclide dosimetry in RANDO head phantom

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