Voxel phantoms and Monte Carlo methods applied to in vivo measurements for simultaneous 241Am contamination in four body regions

Hunt, John; Dantas, Bernardo Maranhão; Lourenço, Maria Cristina da Silva; Azeredo, A. M. G. F.

doi:10.1093/oxfordjournals.rpd.a006300

Cited by 19 publications

(9 citation statements)

References 4 publications

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“…Alternatively, numerical calibration techniques may be applied. Mathematical software combines voxel phantoms and Monte Carlo statistical simulations to model photon transport from the phantom and the detection of photons by a simulated detector (Franck et al., 2003; Hunt et al., 2003; Gómez-Ros et al., 2007; Lopez et al., 2011a). The International Atomic Energy Agency (IAEA, 1996) and the International Commission on Radiation Units and Measurements (ICRU, 2002) have given guidance on the direct measurement of body content of radionuclides.…”

Section: Methods Of Individual and Workplace Monitoringmentioning

confidence: 99%

Section: Body Activity Measurements (In-vivo Measurements)mentioning

confidence: 99%

See 1 more Smart Citation

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Paquet¹,

et al. 2015

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This report is the first in a series of reports replacing Publications 30 and 68 to provide revised dose coefficients for occupational intakes of radionuclides by inhalation and ingestion. The revised dose coefficients have been calculated using the Human Alimentary Tract Model (Publication 100) and a revision of the Human Respiratory Tract Model (Publication 66) that takes account of more recent data. In addition, information is provided on absorption into blood following inhalation and ingestion of different chemical forms of elements and their radioisotopes. In selected cases, it is judged that the data are sufficient to make material-specific recommendations. Revisions have been made to many of the models that describe the systemic biokinetics of radionuclides absorbed into blood, making them more physiologically realistic representations of uptake and retention in organs and tissues, and excretion. The reports in this series provide data for the interpretation of bioassay measurements as well as dose coefficients, replacing Publications 54 and 78. In assessing bioassay data such as measurements of whole-body or organ content, or urinary excretion, assumptions have to be made about the exposure scenario, including the pattern and mode of radionuclide intake, physical and chemical characteristics of the material involved, and the elapsed time between the exposure(s) and measurement. This report provides some guidance on monitoring programmes and data interpretation.

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Section: Methods Of Individual and Workplace Monitoringmentioning

confidence: 99%

Section: Body Activity Measurements (In-vivo Measurements)mentioning

confidence: 99%

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Paquet¹,

et al. 2015

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“…The Monte Carlo method more appropriate to treat complex problems. The ce of the Monte Carlo codes, su [48], EGS4 [49], GEANT, MORSE, PENELOPE, TRIP-OLIS, etc. allows a priori and a posteriori analyses for dissimilar calibration and measurement conditions.…”

Section: The Use Of Virtual Phantoms For Calibrationmentioning

confidence: 99%

Direct Determination of Radionuclides in the Body Optimisation of Measurements Parameters and Results Analysis

Genicot¹,

Fonseca²,

Kramer³

et al. 2011

WJNST

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Whole body counting (WBC) benefits from new types of detectors and methodologies. It has found applications in areas such as in medicine, protection of workers and of population. The design of a WBC facility should be tailored to the type of application. Monte Carlo calculations help to improve the reliability of the calibration of a facility, particularly for non-standard measurements (child, etc.), help in optimizing shielding of counting rooms, preventing large systematic errors and lowering detection limits. In vivo counting may be used to evaluate the distribution of radionuclides in organs for metabolic studies with multiple detectors or with a scan of the body. Reduction of detection levels by background reduction is limited. Improved sensitivity can be obtained by adapting the detector type and size to the measured photon energy. The benefit of comparison exercises and training courses are demonstrated. Further improvements in accuracy can be expected from cooperative works with other techniques: indirect methods (urines and faeces) and passive detectors placed correctly on the body can in the case of high levels of contamination can be used to improve the burden assessment.

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“…Visual Monte Carlo (Hunt et al 2003) is a Monte Carlo code created for calibration of body counters, and dose calculation for internal and external radiation sources.…”

Section: )mentioning

confidence: 99%

Personalised Body Counter Calibration Using Anthropometric Parameters

Pölz

Breustedt

2015

Radiat Prot Dosimetry

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Zusammenfassung AbstractBody counting is a method for in vivo activity assessment applied to the monitoring of people with high risk of radionuclide incorporation. Energy-sensitive radiation detectors are arranged relative to the body to quantify radionuclide deposits in anatomical structures, such as lungs, liver and skeleton. This method depends on the specific detection system and is sensitive to the individual anatomy of the person. Accurate activity estimates, which are the basis for dose calculation, require extensive calibration procedures typically involving experimental measurements of anthropomorphic phantoms conforming to a reference person. Current calibration methods offer personalisation for lung and liver counting only with respect to body mass and height and do not specify uncertainties.This work revises and extends the currently applied personalisation methods using radiation transport simulation in combination with computational phantoms derived from medical imaging data. A framework was developed that allows computation of samples of calibration factors for various anatomies in standard measurement setups and anthropometric parameters quantifying anatomic properties. Those samples are applied to create statistical models to derive personalised calibration factors given specific values of anthropometric parameters measured on the person. This gives better estimates in activity assessment and, thereby, dose calculation while quantifying and reducing uncertainties.The framework was implemented in form of an abstract, modular data model, a software tool for modelling, simulation and evaluation of general body counting scenarios, and a statistical analysis method for correlating anthropometric parameters and calibration factors. This allows efficient and reproducible modelling for virtual measurement reconstruction as well as sensitivity analyses. The framework was applied to the calibration of the In Vivo Measurement Laboratory (IVM) at Karlsruhe Institute of Technology (KIT) comprising four freely arrangeable high-purity germanium detectors in lung, liver, knee and head measurement setups. Because of the interindividual anatomical variations in the applied phantoms and iv additional sensitivity analyses, it was possible to give estimates of the expected uncertainties and to reduce them through an algorithmically reproducible approach on calibration.

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Voxel phantoms and Monte Carlo methods applied to in vivo measurements for simultaneous 241Am contamination in four body regions

Cited by 19 publications

References 4 publications

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Direct Determination of Radionuclides in the Body Optimisation of Measurements Parameters and Results Analysis

Personalised Body Counter Calibration Using Anthropometric Parameters

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