ArticlePDF Available

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

Authors:
  • Instituto de Radioproteção e Dosimetria
  • Instituto de Radioproteção e Dosimetria, Rio de Janeiro, Brazil

Abstract and Figures

A Monte Carlo program, Visual Monte Carlo (VMC) in vivo, was written to simulate photon transport through an anthropomorphic phantom and to detect radiation emitted from the phantom. VMC in vivo uses a voxel phantom provided by Yale University and may be used to calibrate in vivo systems. This paper shows the application of VMC in vivo to the measurement of 241Am deposited simultaneously in the thoracic region, the bones, the liver and in the rest of the body. The percentages of 241Am in the four body regions were calculated using the biokinetic models established by the ICRP, for a single intake via inhalation. The four regions of the voxel phantom were then 'contaminated' in accordance with the calculated percentages. The calibration factor of the in vivo system was then obtained. This procedure was repeated for the radionuclide distributions obtained 5, 30, 120, 240 and 360 days after intake. VMC in vivo was also used to calculate the calibration factor of the in vivo system in which the radionuclide was assumed to be deposited only in the lung, as is normally done. The activities calculated with the radionuclide distributed in the four body regions as a factor of time, and the activities calculated with the radionuclide deposited in the lung only are compared.
Content may be subject to copyright.
549
Radiation Protection Dosimetry Vol. 105, No. 1–4, pp. 549552 (2003)
Published by Nuclear Technology Publishing
2003 Nuclear Technology Publishing
VOXEL PHANTOMS AND MONTE CARLO METHODS APPLIED
TO IN VIVO MEASUREMENTS FOR SIMULTANEOUS
241
Am
CONTAMINATION IN FOUR BODY REGIONS
J. G. Hunt, B. M. Dantas, M. C. Lourenc
¸
o and A. M. G. Azeredo
Institute of Radiation Protection and Dosimetry
Av. Salvador Allende s/n, Recreio
Rio de Janeiro, CEP 22780–160, Brazil
Abstract A Monte Carlo program, Visual Monte Carlo (VMC) in vivo, was written to simulate photon transport through an
anthropomorphic phantom and to detect radiation emitted from the phantom. VMC in vivo uses a voxel phantom provided by
Yale University and may be used to calibrate in vivo systems. This paper shows the application of VMC in vivo to the measurement
of
241
Am deposited simultaneously in the thoracic region, the bones, the liver and in the rest of the body. The percentages of
241
Am in the four body regions were calculated using the biokinetic models established by the ICRP, for a single intake via
inhalation. The four regions of the voxel phantom were then ‘contaminated’ in accordance with the calculated percentages. The
calibration factor of the in vivo system was then obtained. This procedure was repeated for the radionuclide distributions obtained
5, 30, 120, 240 and 360 days after intake. VMC in vivo was also used to calculate the calibration factor of the in vivo system
in which the radionuclide was assumed to be deposited only in the lung, as is normally done. The activities calculated with the
radionuclide distributed in the four body regions as a factor of time, and the activities calculated with the radionuclide deposited
in the lung only are compared.
INTRODUCTION
The Monte Carlo technique and voxel phantoms have
been applied to the problem of calibration of whole
body counters (WBCs) since 1995
(1–4)
. These papers
demonstrate that mathematical phantoms can comp-
lement physical phantoms for routine calibration pur-
poses. At present, the Institute of Radiation Protection
and Dosimetry (IRD) WBC
(5)
is using the Monte Carlo
calibration technique to provide activities that will be
reported as part of the current IAEA whole body inter-
comparison programme.
This paper describes the application of this technique
to the study of a biokinetic model proposed by the ICRP
in ICRP Report 56
(6)
. The case chosen involves a single
intake through inhalation of
241
Am type ‘M’, with an
AMAD of 5 m. The biokinetic model proposed in
ICRP Report 56 was used to evaluate the activity
deposited in each tissue or organ for 5, 30, 120, 240
and 360 days after intake.
The Monte Carlo code, Visual Monte Carlo (VMC)
in vivo, together with the Yale whole body voxel phan-
tom, were then used to calculate the calibration factors
for a Canberra Ge detector placed over the lung, and
over the knee for such a case. The voxel phantom
tissues were mathematically ‘contaminated’ so as to
simulate the simultaneous deposition of
241
Am in the
thoracic region, the bones, the liver and the ‘rest of the
body’. In this case, the ‘rest of the body’ signifies the
remaining soft tissues, the muscle, the adipose tissue
and the skin.
Contact author E-mail: john@ird.gov.br
MATERIALS AND METHODS
The IRD whole body counter
The IRD–CNEN whole body counter uses an array
of four Canberra HPGe detectors for in vivo measure-
ments of low energy radionuclides. The detectors are
20 mm thick, with an active diameter of 50.5 mm, active
areas of 2000 mm
2
, and a 0.6 mm carbon composite
window. The measurements are performed inside a
2.5 m 2.5 m 2.62 m room with 15 cm steel walls,
each covered internally with a 3 mm lead layer, fol-
lowed by a 1.5 mm cadmium layer and finally a 0.5 mm
copper layer. These layers reduce the background count
rate for energies below 200 keV.
VMC in vivo
VMC in vivo was used to simulate a tissue contami-
Table 1. Percentage distribution of
241
Am in four body
regions in relation to the number of days after intake, cal-
culated using the ICRP 56 model.
Days after Distribution of
241
Am (per cent)
intake
Lung Bone Liver Rest
5 58 9 15 18
30 54 14 23 9
120 29 24 34 13
240 15 31 38 16
360 7 37 39 17
J. G. HUNT, B. M. DANTAS, M. C. LOURENCO and A. M. G. AZEREDO
550
nation, to transport the photons through the tissues and
to simulate the detection of the radiation. As the radio-
nuclides of interest for radiation protection fall princi-
pally in the range 0.061.5 MeV, only photoelectric
and Compton interactions were considered. Runs of
5 10
6
histories were performed, which require around
30 minutes on a computer with an Athlon XP (1.8 GHz
clock) CPU.
Calculation of the calibration factors
The
241
Am calibration factors (in Bq cps
1
) are calcu-
lated using the following equation
(3)
:
Calibration factor =
N
photopeak counts
1
DSF P
,
where
N is the total number of photons emitted in
the simulation,
photopeak counts is the number of
photons counted in the photo peak, DSF is the detector
simulation factor or efciency, which in this work is
considered to be equal to 1.0, and P is the yield, which,
for
241
Am, is 0.357. A DSF equal to 1.0 implies that
there are no losses due to photon absorption in the
detector window and no losses due to the electronics.
Real measurements with the HPGe detectors show an
efciency at 60 keV of around 0.95. If required, the cali-
bration factors given in Figure 2 and in the two tables
may be divided by 0.95 to give the true calibration fac-
tors for this detector model.
Figure 1. Visualisation of the body activity for three cases: 5 days after intake (top), 120 days after intake (middle) and 360 days
after intake (bottom) for the knee geometry.
The voxel phantom
For the simulation of in vivo measurement systems,
a voxel phantom with a format of 488 slices each of
192 96 picture elements, was used. Each voxel is a
cube with 3.6 mm sides. The voxel phantom is derived
from a whole body magnetic resonance image (MRI)
scan and was obtained from the Yale University voxel
phantom library that is maintained by I. G. Zubal. The
Yale voxel phantom was modied at the IRD so as to
maintain only the tissues relevant for whole body coun-
ting. For this work, the phantom is divided into the fol-
lowing tissue types: lung, total bone and liver. The other
tissues and muscles are grouped together.
The ICRP biokinetic model
The case chosen for study involves a single intake
through inhalation, of
241
Am type M. The systemic
biokinetic model proposed in ICRP Report 56 was used
to evaluate the percentage of activity deposited in each
of the above mentioned tissue types for 5, 30, 120, 240
and 360 days after intake (see Table 1). The human res-
piratory tract model described in ICRP Publication 66
(7)
was also used.
RESULTS AND DISCUSSION
The graphical representation of the knee counting
geometry for 5, 120 and 360 days after intake is shown
in Figure 1. The relative activities of the lung, liver,
bone and the rest can be seen. The calibration factors
for the lung and knee geometries for
241
Am deposition
in the four body regions were calculated for the ve
THE MONTE CARLO TECHNIQUE AND VOXEL PHANTOMS
551
time intervals, and the results are shown in Figure 2,
which also shows the calibration factors obtained for a
100% deposition of
241
Am in the lung and a 100% depo-
sition of
241
Am in the total bone.
In Table 2, the cps that would be obtained through a
real measurement in the case of a single intake of 1 kBq
of
241
Am are shown. These values are obtained by divid-
10
2
10
1
10
0
0 50 100 150 200 250 300 350 400
knee geometry
lung geometry
6.1 kBq cps
-1
for
241
Am in lung-lung geometry
1.6 kBq cps
-1
for
241
Am in lung-lung geometry
Days after intake
kBq cps
-1
Figure 2. Comparison of calibration factors (kBq cps
1
) for
241
Am in relation to time after intake. The black circles refer to
the lung geometry, and the white circles to the knee geometry.
Table 2. Calculated cps for the lung and knee geometries as a function of time after an intake of 1 kBq of
241
Am type
‘M’.
Days after Total Lung geometry Knee geometry
intake activity
(Bq)
Calibration Cps Lung Lung activity Calibration Cps Bone Bone activity
factor activity calculated factor activity calculated
(kBq cps
1
) (Bq) using (kBq cps
1
) (Bq) using
1.6 kBq cps
1
6.1 kBq cps
1
(Bq) (Bq)
5 91.8 2.54 0.036 53 58 26.4 0.0035 8.3 21
30 71.5 2.73 0.026 39 42 32.4 0.0022 10 13
120 60.3 4.39 0.014 18 22 20.0 0.0030 14 18
240 57.2 6.95 0.0082 8.6 13 13.8 0.0041 18 25
360 55.6 9.58 0.0058 3.4 9.3 12.7 0.0044 21 27
REFERENCES
1. Mallett, M. W., Hickman, D. P., Knuchen, D. A. and Poston J. W. Development of a method for calibrating in vivo measure-
ment systems using magnetic resonance imaging and Monte Carlo computations. Health Phys. 68(6), 773785 (1995).
2. Ishikawa, I. and Uchiyama, M. Estimation of the counting efficiencies for individual subjects in
137
Cs whole body counting,
using voxel phantoms. Radiat. Prot. Dosim. 71(3), 195200 (1997).
3. Hunt, J. G., Mala
´
tova
´
, I. and Folta
´
nova
´
,S.Calculation and measurement of calibration factors for bone-surface seeking low
ing the total body activity by the respective calibration
factor. Table 2 also includes the activities for the lung
and knee geometries obtained from the ICRP model,
and the corresponding activities obtained by using the
calibration factors obtained for the lung phantom
(1.6 kBq cps
1
) and for the bone phantom
(6.1 kBq cps
1
).
A comparison of the activities for the lung and knees,
and the corresponding activities obtained by using the
calibration factors obtained for the lung phantom and
for the bone phantom, show that the question of activity
present in other organs introduces an error in the meas-
ured activity. For the lung geometry, the result is a 10%
overestimation of the activity for the rst 2 months after
intake. For the knee geometry, the result is an approxi-
mately 30% overestimation of the activity 30 days
after intake.
CONCLUSIONS AND FUTURE WORK
If the measured cps values for a real case of
241
Am
incorporation over the time interval of 360 days are
similar to those shown in Table 2, then it can be con-
sidered that the ICRP Report 56 model has been suc-
cessfully checked.
The results conrm that the time after intake is very
important for the interpretation of the values measured
with a WBC. For example, at 5 days, the overestimation
of bone activity by using a bone phantom for calibration
is by a factor of 2.5, falling to 30% during the rst
month. For the lung, the overestimation increases from
10% after 5 days to a factor of 2.7 after 360 days.
J. G. HUNT, B. M. DANTAS, M. C. LOURENCO and A. M. G. AZEREDO
552
energy gamma emitters and determination of
241
Am activity in a real case of internal contamination. Radiat. Prot. Dosim.
82(3), 215-218 (1999).
4. Hunt, J. G., Bertelli, L., Dantas, B. M. and Lucena, E. Calibration of in vivo measurement systems and evaluation of lung
measurement uncertainties using a voxel phantom. Radiat. Prot. Dosim. 76(3), 179184 (1998).
5. Oliveira, C. A. N., Lourenc
¸
o, M. C., Dantas, B. M., Lucena, E. A., Bertelli, L. and Laurer, G. R. The IRD/CNEN whole body
counting facility: background and calibration results. Radiat. Prot. Dosim. 29(3) 203208 (1989).
6. International Commission on Radiological Protection. Age-dependant doses to members of the public from intake of radio-
nuclides: Part 1. ICRP Publication 56. Ann. ICRP 20(2) (Oxford: Pergamon Press) (1989).
7. International Commission on Radiological Protection. Human respiratory tract model for radiation protection. ICRP Publi-
cation 66. Ann. ICRP 24(13) (Oxford: Pergamon Press) (1994).
... The highest complexity level related to a real measurement geometry, including the detectors and their placement with respect to the skull phantom ( Vrba et al 2015). All three intercomparison parts were addressed by 15 or 16 participants, mostly using the MCNPX code (Pelowitz 2005), but there were also results produced using other codes, namely EGS4 (Nelson et al 1985), Geant4 ( Agostinelli et al 2003) and VNC ( Hunt et al 2003). ...
Article
Working Group (WG) 6 "Computational Dosimetry" of the European Radiation Dosimetry Group (EURADOS) promotes good practice in the application of computational methods for radiation dosimetry in radiation protection and the medical use of ionizing radiation. Its cross-sectional activities within the association cover a large range of current topics in radiation dosimetry, including more fundamental studies of radiation effects in complex systems. In addition, WG 6 also performs scientific research and development as well as knowledge transfer activities, such as training courses. Monte Carlo techniques, including the use of anthropomorphic and other numerical phantoms based on voxelized geometrical models, have a strong part in the activities pursued in WG 6. However, other aspects and techniques, such as neutron spectra unfolding, play an important role as well. A number of intercomparison exercises have been carried out in the past to provide information on the accuracy with which computational methods are applied and whether best practice is being followed. Within the exercises that are still ongoing, the focus has changed towards assessing the uncertainty that can be achieved with these computational methods. Furthermore, the future strategy of WG 6 also includes an extension of the scope toward experimental benchmark activities and evaluation of cross-sections and algorithms, with the vision of establishing a gold standard for Monte Carlo methods used in medical and radiobiological applications.
... The influence of the radionuclide biokinetics was investigated by de Carlan et al. for the Zubal voxel phantom (de Carlan et al., 2007), where they found that realistic vs. homogeneous radionuclide distributions within the phantom led to differences up to a factor of 3 in the detection efficiencies. The impact of radionuclide biokinetics on the detection efficiencies has been quantified using voxel phantoms (Hunt et al., 2003) and software interfacing numerical phantoms with biokinetic models has also been developed (Lamart et al., 2007). However, radionuclide biokinetics was not considered in this study to allow a general comparison between the MDA obtained with voxel and physical phantoms, as the latter do not allow for an anatomically accurate radionuclide distribution. ...
Article
Full-text available
The establishment of an in vivo internal monitoring programme requires the use of phantoms to represent an activity distribution of an incorporated radionuclide within the body. The aim of this study was to quantify the impact of the phantom geometry on the minimum detectable activity (MDA) of an incorporated radionuclide. The MDA was assessed for two instruments: a conventional radiation protection instrument and a portable gamma spectrometer. Four phantoms were considered: two physical phantoms, a simplified torso phantom and a commercial whole body phantom, as well as two numerical phantoms, the reference adult male and female voxel phantoms published by the International Commission on Radiological Protection (ICRP). The phantoms were loaded with activity at the level of the thorax and abdomen using reference sources of 57 Co, 133 Ba, 137 Cs, 60 Co and 152 Eu. The MDA for both instruments was experimentally assessed using the two physical phantoms. The experimental setup was modelled in GEANT4 and the simulated instrument responses were validated by the experimental data. The Monte Carlo model was then used to compute the instruments response and corresponding MDA when using the ICRP voxel phantoms. The simplified torso phantom provided one of the highest MDA estimates, up to a factor of 5 higher than the ones obtained with the voxel phantoms when considering a 57 Co source. Depending on the considered source distribution within the phantoms, physical phantoms may lead to an underestimation of the MDA when compared to more complex and anatomically accurate numerical phantoms. This work presents a quantitative comparison between the MDA obtained with different phantoms and radionuclide distributions.r
... In this paper, the internal contamination of individuals with 137 Cs or 131 I such as that seen after a large scale accident at a nuclear Power plant (NPP) or spent fuel pond is simulated, and the calibration factors for hand-held dose rate meters in kBq per µSv/h in a given organ or tissue were calculated using the Monte Carlo method. The MCNPx code ( Pelowitz, 2011) and the freely available Monte Carlo program Visual Monte Carlo (VMC) in-vivo ( Gómez-Ros et al., 2008;Hunt et al., 2002) were used for the modelling. ...
Article
Assessing the intake of radionuclides after an accident in a nuclear power plant or after the intentional release of radionuclides in public places allows dose calculations and triage actions to be carried out for members of the public and for emergency response teams. Gamma emitters in the lung, thyroid or the whole body may be detected and quantified by making dose rate measurements at the surface of the internally contaminated person. In an accident scenario, quick measurements made with readily available portable equipment are a key factor for success. In this paper, the Monte Carlo program Visual Monte Carlo (VMC) and MCNPx code are used in conjunction with voxel phantoms to calculate the dose rate at the surface of a contaminated person due to internally deposited radionuclides. A whole body contamination with ¹³⁷Cs and a thyroid contamination with ¹³¹I were simulated and the calibration factors in kBq per µSv/h were calculated. The calculated calibration factors were compared with real data obtained from the Goiania accident in the case of ¹³⁷Cs and the Chernobyl accident in terms of the ¹³¹I. The close comparison of the calculated and real measurements indicates that the method may be applied to other radionuclides. Minimum detectable activities are discussed.
... Table 1 shows the general features of the phantoms. The VMC 'in vivo' program version developed by John Hunt at IRD (Hunt et al 2003) is used to calibrate the Whole Body Counter laboratory of the Brazilian Institute of Radioprotection and Dosimetry (IRD) in Rio de Janeiro, Brazil. VMC uses the ICRP and Yale voxel phantoms to calculate the calibration factors of a simulated WBC system. ...
Article
Full-text available
A Whole Body Counter (WBC) is a facility to routinely assess the internal contamination of exposed workers, especially in the case of radiation release accidents. The calibration of the counting device is usually done by using anthropomorphic physical phantoms representing the human body. Due to such a challenge of constructing representative physical phantoms a virtual calibration has been introduced. The use of computational phantoms and the Monte Carlo method to simulate radiation transport have been demonstrated to be a worthy alternative. In this study we introduce a methodology developed for the creation of realistic computational voxel phantoms with adjustable posture for WBC calibration. The methodology makes use of different software packages to enable the creation and modification of computational voxel phantoms. This allows voxel phantoms to be developed on demand for the calibration of different WBC configurations. This in turn helps to study the major source of uncertainty associated with the in vivo measurement routine which is the difference between the calibration phantoms and the real persons being counted. The use of realistic computational phantoms also helps the optimization of the counting measurement. Open source codes such as MakeHuman and Blender software packages have been used for the creation and modelling of 3D humanoid characters based on polygonal mesh surfaces. Also, a home-made software was developed whose goal is to convert the binary 3D voxel grid into a MCNPX input file. This paper summarizes the development of a library of phantoms of the human body that uses two basic phantoms called MaMP and FeMP (Male and Female Mesh Phantoms) to create a set of male and female phantoms that vary both in height and in weight. Two sets of MaMP and FeMP phantoms were developed and used for efficiency calibration of two different WBC set-ups: the Doel NPP WBC laboratory and AGM laboratory of SCK-CEN in Mol, Belgium.
... 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. ...
Book
Full-text available
This book describes the development of a new method for personalisation of efficiency factors in partial body counting. Its achieved goal is the quantification of uncertainties in those factors due to variation in anatomy of the measured persons, and their reduction by correlation with anthropometric parameters. The method was applied to a detector system at the In Vivo Measurement Laboratory at Karlsruhe Institute of Technology using Monte Carlo simulation and computational phantoms. © 2014 Karlsruher Institut fur Technologie (KIT). All rights reserved.
Article
In-vivo measurements of ²⁴¹Am using HPGe detectors become complicated when the active adjacent source organs interfere with the target organ measurements. It is important to calculate the contribution of confounding organs to estimate the activity of the target organ accurately. In the current study, numerical simulations were performed using FLUKA Monte Carlo code and International Commission on Radiological Protection (ICRP) computational reference phantoms to determine the calibration matrices consisting of the calibration and cross-talk coefficients for three interfering organs namely, lungs, liver and skeleton. It was found that the interference from adjacent organs contaminated with ²⁴¹Am was found to be significant in the case of lungs and liver. Knee monitoring was least influenced by the activity possessed by other source organs due to their anatomical distance from the knee. A comparison between lung and liver coefficients obtained from the Lawrence Livermore National Laboratory (LLNL) torso phantom and thorax phantom derived from ICRP adult male voxel phantom was performed. It was found that variations in coefficients obtained from simulations and experiments range between 2% to 48%. The differences were attributed to the uncertainties arising from the composition of the phantoms and detectors, size and shape of organs, positional errors, and source distribution. A comparison of calibration matrices of adult male and adult female thorax voxel phantoms revealed that most of the coefficients were larger for the female thorax phantom owing to the lesser bulk of attenuating tissues on the chest. The coefficients obtained from simulations for different phantoms also showed that the organ activity estimation can be significantly affected by the subject morphology.
Article
Full-text available
The production 18F-FDG for positron emission tomography (PET) has consistently increased over the past two decades. The risk of internal contamination at 18F-FDG production facilities exists. A setup for evaluation of the 18F-FDG activity incorporated into the OEW brain, called Head Counting System (HCS), was presented in previous works. In this study, the whole body counter setup (WBC) was evaluated for monitoring 18F incorporations. The Monte Carlo Virtual Software (VMC in-vivo) and the MCNPx code were used to assess the system calibration coefficient (CC). Three 18F distributions were simulated: i) uniformly distributed in soft tissue (UDST); ii) Na18F biodistribution (NAFB); and iii) 18F-FDG biodistribution (FDGB). The calibration coefficient of WBC was compared to the current head counting system CC under the same biodistribution conditions. The ICRP male reference voxelized phantoms (RCP_AM) was used in the simulations. The results showed that the WBC setup was more efficient than the head counter for all the studied 18F distributions: UDST = 1060 %, FDGB = 488 % and NAFB = 340 %. Despite this, especially for 18F-FDG, the possibility of bladder voiding before measurement can lead to considerable uncertainties when the WBC setup is used. On the other hand, bladder activity does not show great influence the calibration coefficient of the head counting system. Future work will evaluate the WBC sources of uncertainties in the measurement of 18F incorporated activity.
Chapter
This document is part of Volume 4 'Radiological Protection' of Landolt-Börnstein - Group VIII Advanced Materials and Technologies. Since human beings do not possess any sense for the detection of ionizing radiation, they must entirely rely on special instruments in order to prevent or control any harmful radiation exposure or intake of radioactivity from the outset. Therefore, reliable instruments and methods for radiation detection and measurement form the precondition for the safe handling of radiation and radioactivity in medicine, scientific research, industry, and nuclear energy production. The primary tasks of radiation protection measurements can roughly be divided into dose and activity measurements employed to prevent and control hazard to man from ionizing radiation (external exposure) or the incorporation of radioactivity (internal exposure), respectively. The purpose of this document is to give a short overview over the application of radiation detectors in practice to monitor and quantify internal exposures in vivo.
Book
Abstract –: 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.
Article
Full-text available
A aplicação de radiações ionizantes em processos industriais vem assumindo um papel cada vez mais importante no cenário nacional. A Radiografia Industrial é uma das técnicas mais empregadas na realização de ensaios não-destrutivos, que verificam a integridade (existência de imperfeições, trincas ou rachaduras internas) de vasos de contenção, caldeiras industriais, tubulações ou soldas em gasodutos e oleodutos. Esse tipo de radiografia pode ser realizada com radiação X ou gama, sendo que em cerca de noventa por cento dos casos esse procedimento é realizado utilizando-se fontes de 192 Ir, emissor gama com energia média de 380 KeV. A esta prática dá-se o nome de Gamagrafia. A Norma CNEN-NN-6.04 (1) da Comissão Nacional de Energia Nuclear (CNEN), determina que para trabalhos de Radiografia Industrial realizados em zonas urbanas, suburbanas e rurais, ou seja, áreas onde possa existir a presença de Indivíduos do Público, faz-se necessário a elaboração por parte das Empresas, de um Plano Específico de Radioproteção para cada obra, adicionando assim ao Plano Geral de Radioproteção da Empresa medidas de radioproteção complementares. Como os trabalhos em Zonas Urbanas e afins podem ocasionar exposição à fonte de radiação não só para os Operadores mas também para Indivíduos do Público, é interessante que os valores de doses ocupacionais possam ser devidamente avaliados. O trabalho apresentado a seguir representa o primeiro passo no sentido de simular doses ocupacionais em zonas urbanas. É feita uma intercomparação entre os Códigos de Monte Carlo VMC (2) e MCNP (3) , com o objetivo de testar a viabilidade de se utilizar o primeiro para simular valores de doses ocupacionais em situações de rotina e de emergência em tempo real.
Article
Full-text available
A whole body counter installation was constructed and calibrated for the determination of small amounts of gamma/X ray photon emitters in the energy range from 10 ke V to 3 Me V. Three phoswich detectors, as well as one 20.3 cm diam. x 102 cm thick NaI(Tl) and one 7.6 cm x 7.6 cm collimated NaI(Tl), were installed inside a steel monitoring room. An additional 'graded Z' lining consisting of Pb, Cd and Cu has been added to the interior of the room. The facility was calibrated using specific, anthropomorphic phantoms for each site of measurement. This paper will discuss the results of background and calibration measurements performed at this facility.
Article
Full-text available
A voxel phantom has been developed to simulate in vivo measurement systems for calibration purposes. The calibration method presented here employs a mathematical phantom, produced in the form of volume elements (voxels), obtained through magnetic resonance images of the human body. The calibration method uses the Monte Carlo technique to simulate the tissue contamination, to transport the photons through the tissues and to simulate the detection of the radiation. The program simulates the transport and detection of photons between 0.035 and 2 MeV and uses, for the body representation, a voxel phantom with a format of 871 'slices' each of 277 x 148 picture elements. The Monte Carlo code is applied to the calibration of in vivo systems and to estimate differences in counting efficiencies between homogeneous and non-homogeneous radionuclide distributions in the lung. Calculations show a factor of 20 between deposition of 241Am at the back compared with the front of the lung.
Article
Full-text available
A voxel phantom has been developed to simulate in vivo measurement systems for calibration purposes. The calibration method presented here employs a mathematical phantom, produced in the form of volume elements (voxels), obtained through magnetic resonance images of the human body. The voxel phantom has a format of 871 'slices' each of 277 x 148 picture elements. The calibration method uses the Monte Carlo technique to simulate the tissue contamination, to transport the photons through the tissues and to simulate the detection of the radiation. The program was applied to obtain calibration factors for the in vivo measurement of 241Am deposited on the cortical bone surface of a real contamination case, and to the simulation of in vivo measurements of 241Am deposited on the cortical bone surface of three head phantoms, as measured with a germanium detector. The calculated and real activities in all four cases were found to be in good agreement. The results indicate that mathematical phantoms could eventually substitute for physical phantoms in the calibration of in vivo measurements for low energy radionuclides.
Article
A method is described to estimate the counting efficiency appropriate to the body size of each individual subject in 137Cs whole-body counting, using voxel phantoms. Individual voxel phantoms approximate to the body sizes of subjects were prepared by expanding and contracting the standard voxel phantom that corresponds to a Japanese standard adult male. The individual phantom was made to have the same body height and weight as those of each individual subject. For a whole-body counter at NIRS (Japan), the counting efficiencies for ten subjects were calculated, using the voxel phantoms and a Monte Carlo simulation code. The differences in the counting efficiency between each individual phantom and a conventional phantom ranged from -5 to +12%. The counting efficiency is larger in small body sizes than in large body sizes. The results indicate that body burdens tended to be overestimated in subjects of small body sizes.
Article
In 1984, the International Commission on Radiological Protection (ICRP) appointed a task group of Committee 2 to review and revise, as necessary, the ICRP Dosimetric Model for the Respiratory System. The model was originally published in 1966, modified slightly in Publication No. 19, and again in Publication No. 30 (in 1979). The task group concluded that research during the past 20 y suggested certain deficiencies in the ICRP Dosimetric Model for the Respiratory System. Research has also provided sufficient information for a revision of the model. The task group's approach has been to review, in depth, morphology and physiology of the respiratory tract; deposition of inhaled particles in the respiratory tract; clearance of deposited materials; and the nature and specific sites of damage to the respiratory tract caused by inhaled radioactive substances. This review has led to a redefinition of the regions of the respiratory tract for dosimetric purposes. The redefinition has a morphologic and physiological basis and is consistent with observed deposition and clearance of particles and with resultant pathology. Regions, as revised, are the extrathoracic (E-T) region, comprising the nasal and oral regions, the pharynx, larynx, and upper part of the trachea; the fast-clearing thoracic region (T[f]), comprising the remainder of the trachea and bronchi; and the slow-clearing thoracic region (T[s]), comprising the bronchioles, alveoli, and thoracic lymph nodes. A task group report will include models for calculating radiation doses to these regions of the respiratory tract following inhalation of representative alpha-, beta-, and gamma-emitting particulate and gaseous radionuclides. The models may be implemented as a package of computer codes available to a wide range of users. This should facilitate application of the revised human respiratory tract model to worldwide radiation protection needs. (C)1989Health Physics Society
Article
Research efforts towards developing a new method for calibrating in vivo measurement systems using magnetic resonance imaging (MRI) and Monte Carlo computations are discussed. The method employs the enhanced three-point Dixon technique for producing pure fat and pure water MR images of the human body. The MR images are used to define the geometry and composition of the scattering media for transport calculations using the general-purpose Monte Carlo code MCNP, Version 4. A sample case for developing the new method utilizing an adipose/muscle matrix is compared with laboratory measurements. Verification of the integrated MRI-MCNP method has been done for a specially designed phantom composed of fat, water, air, and a bone-substitute material. Implementation of the MRI-MCNP method is demonstrated for a low-energy, lung counting in vivo measurement system. Limitations and solutions regarding the presented method are discussed.