<scp>MABDOSE.</scp> I: Characterization of a general purpose dose estimation code

Johnson, Timothy K.; McClure, David; McCourt, Steven

doi:10.1118/1.598636

Cited by 26 publications

(9 citation statements)

References 9 publications

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“…Particularly, in radioimmunotherapy ͑RIT͒, data gathered from SPECT or PET images can provide important information related to the spatial distribution of radionuclides administered to patients in diagnosis and therapy. [1][2][3][4] Also, patient-specific anatomic information, obtained from CT and MRI images can be used for the construction of voxel-based geometric models of the human body, [5][6][7] where previously only models using approximate geometric constructs have been available. 8,9 The simulation of radiation transport by Monte Carlo techniques has become an important basic tool for dose calculations, and several program packages are currently available to treat problems in radiation protection and RIT dosimetry.…”

Section: Introductionmentioning

confidence: 99%

Absorbed fractions in a voxel‐based phantom calculated with the MCNP‐4B code

et al. 2000

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A new approach for calculating internal dose estimates was developed through the use of a more realistic computational model of the human body. The present technique shows the capability to build a patient-specific phantom with tomography data (a voxel-based phantom) for the simulation of radiation transport and energy deposition using Monte Carlo methods such as in the MCNP-4B code. MCNP-4B absorbed fractions for photons in the mathematical phantom of Snyder et al. agreed well with reference values. Results obtained through radiation transport simulation in the voxel-based phantom, in general, agreed well with reference values. Considerable discrepancies, however, were found in some cases due to two major causes: differences in the organ masses between the phantoms and the occurrence of organ overlap in the voxel-based phantom, which is not considered in the mathematical phantom.

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Section: Introductionmentioning

confidence: 99%

Absorbed fractions in a voxel‐based phantom calculated with the MCNP‐4B code

et al. 2000

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“…Many software tools have been created to facilitate these calculations. [15][16][17][18][19][20][21][22][23][24][25][26][27][28][29][30][31] However, many of these programs have limited functionality and either (i) do not provide tools to perform all of the necessary steps from image analysis to determination of TIACs, to calculation of final dose estimates, or (ii) contain only specific tools that do not give enough versatility to be applicable for use with different dosimetry protocols.…”

Section: Ia Background To Internal Dose Calculationsmentioning

confidence: 99%

JADA: A graphical user interface for comprehensive internal dose assessment in nuclear medicine

2013

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“…The Mabdose program [153][154][155], starting with a reference man, allows the definition of a spherical tumour target for which 'on the fly' Monte-Carlo calculations are made.…”

Section: Dosimetry For Organs and Tissuesmentioning

confidence: 99%

Dosimetry and Microdosimetry of Targeted Radiotherapy

Bardiès

Pihet²

2000

CPD

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Dosimetry in targeted radiotherapy (TR) uses different calculation methods, whose degree of refinement is closely conditioned by the particular objective sought. It is more generally performed to establish a correlation between the quantity of radiation delivered to a target and the biological damage observed or that can be reliably predicted. It can thus be used to optimise treatments and allow comparison of different therapeutic approaches, as well as to study the basic methods of irradiation of biological matter. Two broad types of investigations can be found in the literature: microdosimetric ones (stochastic approaches used to study energy deposits) and macrodosimetric ones (non-stochastic or deterministic approaches). The mathematical formalism is consistent between these two types, and the calculation methods currently used are often similar. This review presents different approaches to the dosimetry of radionuclides used in TR. The introduction defines the general problem, the role of dosimetry in TR and the specific problems raised by targeting (non-uniformity of source distributions). The first part considers the types of calculation methods found in TR in relation to the basic quantities used to represent stochastic energy deposit on a cellular scale. In particular, it compares the formalism and the methods used in microdosimetric or conventional macrodosimetric approches. Although microdosimetry, or even track structure calculations, can provide the basic elements for modelling the absorbed dose process, a simplified dosimetric approach may be adequate to describe the phenomena observed. The scheme proposed by the MIRD committee relates to such an approach and is presented together with other methods allowing the calculation of the mean dose delivered (analytic methods, dose point kernels, Monte-Carlo, etc.). The second part shows the application range for the various methods, providing selected examples of dosimetric approaches in TR on different scales, from the organ (or tissues) to the cell or even DNA, and a brief presentation of bone marrow dosimetry.

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MABDOSE. I: Characterization of a general purpose dose estimation code

Cited by 26 publications

References 9 publications

Absorbed fractions in a voxel‐based phantom calculated with the MCNP‐4B code

Absorbed fractions in a voxel‐based phantom calculated with the MCNP‐4B code

JADA: A graphical user interface for comprehensive internal dose assessment in nuclear medicine

Dosimetry and Microdosimetry of Targeted Radiotherapy

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