A dose point kernel database using GATE Monte Carlo simulation toolkit for nuclear medicine applications: Comparison with other Monte Carlo codes

Papadimitroulas, Panagiotis; Loudos, George; Nikiforidis, George; Kagadis, George C.

doi:10.1118/1.4737096

Cited by 91 publications

(84 citation statements)

References 31 publications

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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%

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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Section: Introductionmentioning

confidence: 98%

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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“…Now we aim to estimate the dose with respect to the materials used for proton irradiation. So, these are analyzed by Bragg-Gray cavity theory [16] which deals with stopping power of particles is energy absorbed per unit mass is weighted ratio of mass stopping power.…”

Section: Iii1 Dose Estimationmentioning

confidence: 99%

Geant4 - Study of Dose Curve Parameters of Tumor in Human Tissues Using Passive Proton Beam

Bhatnagar

Sirisha²

2014

2014 International Conference on Computational Intelligence and Communication Networks

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A detailed Geant4 based study of the proton beam passing through different Inhomogenities in a human phantom is carried out. Whenever a proton beam is radiated through the tumor region a significant influence over the stopping power and the depth-dose distribution of the proton energy can be observed due to the adjacent materials. The effect of the heterogeneous medium in tumor has been studied by several groups to assess the ability of beam convolution which predicts the dose required. Adipose, bone and soft tissues materials are considered for the present study. The human organs along with the positioning of the tumor region were designed. The suitable energy range for each tumor of the human organ was optimized. The study was also followed with thickness variation of each material from 0.1 cm to 1.0 cm. Various parameters of the Bragg curve were computed i.e. Bragg peak position, range, penumbra width, full width at half maximum and dose of Bragg curve. A significant shift in the Bragg peak position is observed in each case i.e., approx. -0.36% for muscular skeleton, -0.44% for soft tissue.

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“…Indeed, ADs may be estimated by means of several methods, such as the MIRD approach using S-values for doses at organ-level [7, 8], dose point kernel (DPK)-based convolution [9–11], or Monte Carlo (MC) for doses at pixel-level. MC is considered the reference method, and several comparisons with the others methods were performed and analyzed [10, 12–14]. …”

Section: Introductionmentioning

confidence: 99%

3D absorbed dose distribution estimated by Monte Carlo simulation in radionuclide therapy with a monoclonal antibody targeting synovial sarcoma

et al. 2017

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BackroundRadiolabeled OTSA101, a monoclonal antibody targeting synovial sarcoma (SS) developed by OncoTherapy Science, was used to treat relapsing SS metastases following a theranostic procedure: in case of significant 111In-OTSA101 tumor uptake and favorable biodistribution, patient was randomly treated with 370/1110 MBq 90Y-OTSA101. Monte Carlo-based 3D dosimetry integrating time-activity curves in VOI was performed on 111In-OTSA101 repeated SPECT/CT. Estimated absorbed doses (AD) in normal tissues were compared to biological side effects and to the admitted maximal tolerated absorbed dose (MTD) in normal organs. Results in the tumors were also compared to disease evolution.ResultsBiodistribution and tracer quantification were analyzed on repeated SPECT/CT acquisitions performed after injection of 111In-OTSA101 in 19/20 included patients. SPECT images were warped to a common coordinates system with deformable registration. Volumes of interest (VOI) for various lesions and normal tissues were drawn on the first CT acquisition and reported to all the SPECT images. Tracer quantification and residence time of 111In-OTSA101 in VOI were used to evaluate the estimated absorbed doses per MBq of 90Y-OTSA101 by means of Monte Carlo simulations (GATE). A visual scale analysis was applied to assess tumor uptake (grades 0 to 4) and results were compared to the automated quantification. Results were then compared to biological side effects reported in the selected patients treated with 90Y-OTSA101 but also to disease response to treatment.After screening, 8/20 patients were treated with 370 or 1110 MBq 90Y-OTSA101. All demonstrated medullary toxicity, only one presented with transient grade 3 liver toxicity due to disease progression, and two patients presented with transient grade 1 renal toxicity. Median absorbed doses were the highest in the liver (median, 0.64 cGy/MBq; [0.27 −1.07]) being far lower than the 20 Gy liver MTD, and the lowest in bone marrow (median, 0.09 cGy/MBq; [0.02 −0.18]) being closer to the 2 Gy bone marrow MTD. Most of the patients demonstrated progressive disease on RECIST criteria during patient follow-up. 111In-OTSA101 tumors tracer uptake visually appeared highly heterogeneous in inter- and intra-patient analyses, independently of tumor sizes, with variable kinetics. The majority of visual grades corresponded to the automated computed ones. Estimated absorbed doses in the 95 supra-centimetric selected lesions ranged from 0.01 to 0.71 cGy per injected MBq (median, 0.22 cGy/MBq). The maximal tumor AD obtained was 11.5 Gy.Conclusions3D dosimetry results can explain the observed toxicity and tumors response. Despite an intense visual 111In-OTSA101 liver uptake, liver toxicity was not the dose limiting factor conversely to bone marrow toxicity. Even though tumors 111In-OTSA101 avidity was visually obvious for treated patients, the low estimated tumors AD obtained by 3D dosimetry explain the lack of tumor response.

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A dose point kernel database using GATE Monte Carlo simulation toolkit for nuclear medicine applications: Comparison with other Monte Carlo codes

Cited by 91 publications

References 31 publications

Monte Carlo and experimental internal radionuclide dosimetry in RANDO head phantom

Monte Carlo and experimental internal radionuclide dosimetry in RANDO head phantom

Geant4 - Study of Dose Curve Parameters of Tumor in Human Tissues Using Passive Proton Beam

3D absorbed dose distribution estimated by Monte Carlo simulation in radionuclide therapy with a monoclonal antibody targeting synovial sarcoma

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