Measuring and Monte Carlo Modelling of X-Ray and Gamma-Ray Attenuation in Personal Radiation Shielding Protective Clothing

A collection of personal protective equipment (PPE), suitable for use in case of accident in nuclear facilities or radiological emergencies, was gathered at the National Institute for Nuclear, Chemical and Biological Protection, Czech Republic. The shielding characteristics of the various PPE materials were measured via narrow geometry spectral attenuation measurements with point radionuclide sources covering a broad range of photon energies. Photon relative penetration and attenuation for relevant energies of the spectra were the principal experimentally determined quantities for tested PPE. Monte Carlo simulations in the MCNPX™ code were carried out to determine photon attenuation for respective energies in the tested PPE, and the results were compared to those determined experimentally. Energy depositions in a unit volume of an ORNL phantom were simulated in a radioactive aerosols atmospheric environment to determine effective doses both for the whole body and in various organs in the human torso during exposure to different dispersed radioactive aerosols while wearing one of the PPE protecting against X- and gamma-ray. This work aimed to determine the effective dose and its decrease for individual PPE protecting against X- and gamma-ray.


Introduction
Some samples of personal protective equipment (PPE), protecting against X-and gamma-ray, were collected and tested at the National Institute for NBC Protection (SUJCHBO v.v.i.), Czech Republic. is type of PPE can be used by first responders in emergencies such as an accident during radioactive material transportation, terrorist incidents involving radiological dispersal devices (RDD) or nuclear weapons, or by specialised emergency response workers during accidents in nuclear facilities. e authors are not aware of any other published studies concerning X-and gamma-ray attenuation in PPE. e collection of PPE protecting against X-and gammaray due to the presence of shielding layers comprising heavy metals or their alloys can be divided into two groups: (a) body overalls, covering the whole body and (b) local garments, primarily covering the torso and shielding radiationsensitive body organs, together with nonworn equipment, such as a radiation protection shield. OPCH-90 PPE (without a shielding layer) was chosen as a reference PPE. Table 1 presents individual tested PPE together with their parameters from the manufacturers' materials and experimentally determined density thicknesses.
Relative penetration and attenuation of X-and gammaray, penetrating the samples and originating from different radionuclide point sources, were determined for a broad energy range, together with mass attenuation coefficients, which describe the attenuating qualities of shielding layer materials in individual PPE. Corresponding lead equivalents of individual shielding layers, which express the thickness of the equally attenuating lead sheet, were calculated as well.
e experimentally determined values of these abovementioned quantities for the first part of the collection of PPE protecting against X-and gamma-ray were presented by Kozlovska [2].
following quantities were simulated: relative penetration and attenuation of monoenergetic photons by individual shielding layers and energy deposition in a unit volume of the ORNL phantom while wearing or not-wearing an individual PPE protecting against X-and gamma-ray. e X-and gamma-ray penetration rates in simulated shielding layer material of individual PPE were determined for the main energies of the spectra. e decrease of effective dose both in the whole body and, due to the presence of PPE, the human torso alone were also assessed by the MC modelling of a human body during exposure to selected dispersed radioactive aerosols.

Measurement of X-and Gamma-Ray Spectra.
e spectra of X-and gamma-ray, penetrating tested PPE samples and originating from different radionuclide point sources, were measured by two handheld spectrometers: an InSpector 1000 with detachable IPROL-1 scintillation LaBr 3 probe, and a Falcon 5000 HPGe detector, both manufactured by Canberra Industries, Inc., USA.
Samples of tested PPE were placed on a holder between the source and the detector at the defined distance to meet the lowest possible dead time of the detector and avoid false pulse coincidence. Photon spectra were measured on a testing bench, which enables the precise coaxial narrow beam geometry settings of the source, the detector, and the set of both outer and inner cylindrical collimators ( Figure 1). Outer collimators were made from lead, and their outer and inner diameters were 16.5 cm and 6.0 cm, respectively; the lengths were 22.5 cm and 40.5 cm, respectively, in the case of IPROL-1 LaBr 3 probe measurement, which was inserted into the collimator. Inner collimators were also made of lead at lengths of 8.5 cm, and their outer and inner aperture diameters were 6.0 cm and 1.2 cm, respectively. e narrow beam geometry setting was used for spectra measurement to minimise the number of scattered photons contributing to the measured spectra unwantedly influencing peak areas and causing a build-up effect.
To cover the wide photon energy range from 30.5 keV to 1,408 keV, the following radioactive point sources activation ranging from 9.5 to 40.0 MBq were used: 241 Am, 133 Ba, 152 Eu, 137 Cs, and 60 Co.
Measurement live times ranged from 120 to 1,800 s to obtain net peak areas for all significant sufficiently high fullenergy peaks, achieving their relative uncertainty below 1%.
Measured spectra were subsequently analysed using Genie 2000 Gamma Analysis Software v. 3.2, manufactured by Canberra Industries, Inc. For the primary spectra energies, corresponding to the main peaks of total absorption, photon penetration and attenuation rates in a tested PPE sample were determined. ese quantities were determined via comparing net peak areas in the spectra, measured with the sample placed between the source and the detector, and the corresponding net peak areas in the spectra, measured without any samples, for the same time between the source and the detector. e energy dependency of mass attenuation coefficients was determined from the relative attenuation and experimentally assessed density thicknesses of individual PPE samples to describe shielding qualities of individual shielding layer materials. For each tested sample, a lead equivalent, which sets the thickness of the equally attenuating lead sheet, was determined using the values of the lead mass attenuation coefficient, stated by Johnson and Birty [3]. Mean lead equivalents for individual PPE protecting against X-and gamma-ray was set as mean of lead equivalents determined for the individual energies of significant peaks, except for absorption edges.
Together with the spectra of photons penetrating tested PPE samples, the spectra of photons penetrating a lead sheet (thickness of 1.25 mm) were similarly measured, and the same quantities were determined to test the measurement and spectra evaluation methods.

Radon-Aerosol Chamber.
e Radon-Aerosol Chamber (RAC) at SUJCHBO v.v.i. we used for PPE testing in a dispersed radioactive atmosphere is a gas-tight testing box of 10 m 3 volume with dimensions of 250 cm (length) × 200 cm (width) × 200 cm (height), strictly separated from the ambient atmosphere. e RAC enables the creation of a stable atmosphere containing high concentrations of radioactive or nonradioactive aerosol particles under various physical conditions. It is also possible for the created aerosol particles to be sampled and measured externally. e RAC parameters are described by Burian [4].

Monte Carlo Simulations.
Monte Carlo (MC) simulations were performed using the general-purpose MC code MCNPX ™ version 2.7.E [5]. Full photon and electron transport and the detailed treatment of bremsstrahlung radiation were considered in the whole volume of the RAC. Photon transport utilised the MCPLIB04 photoatomic data library described by White [6], and the low-energy cutoff was set to 10 keV. Electron transport utilised the el03 library described by Adams [7], and the low-energy cutoff was set to 50 keV.

Simulations of PPE Materials.
e elemental compositions of PPE materials necessary for input to the MC model were taken from the results of X-ray fluorescence spectrometry (XRF) and scanning electron microscopy (SEM) measurements. In addition, during the later analysis, energydispersive X-ray spectrometry was also applied to collect additional material information.
A simple MC model consisting of a point source emitting monoenergetic photons perpendicularly to a layer of PPE material was used to calculate relative penetration in individual PPE samples. Material relative penetration for each photon energy was obtained using an F1-type tally located behind the layer counting the number of photons (per one photon emitted from the source) that did not undergo interaction in the layer. e statistical uncertainty of the F1tally results was 0.1%. Consequently, the relative attenuation and relative penetration at different energies were compared to those measured experimentally.
For input to the MC model, the mass density of the samples was determined by finding the best match between measured and calculated relative penetration, keeping the elemental composition fixed.

Simulations of Effective
Dose. MC simulations of energy deposition in a unit volume of an ORNL phantom described by Eckerman et al. [8] were performed in the chosen dispersed radioactive aerosol environment in the RAC. e ORNL phantom was positioned in a standing position at the centre of the RAC, and it was modelled to either wear one of the simulated PPE protecting against X-and gamma-ray (respectively, the simulated PPE together with a PPE preventing radioactive contamination over it in the case of local PPE protecting against X-and gamma-ray), or to solely wear PPE preventing radioactive contamination. e following dispersed radionuclides were simulated: 99m Tc, 131 I, 137 Cs, 140 La, and 24 Na. 131 I and 137 Cs radionuclides emit both beta particles and gamma-ray of medium energies, while 140 La and 24 Na radionuclides emit both beta particles and gamma ray of high energies. However, the 99m Tc radionuclide only emits gamma ray of low energy. Both gamma and beta contributions to the effective dose were taken into account in the simulations. Energy distributions were taken from Radiological Toolbox [9], which contains data from the ICRP 38 publication [10].
ree radiation sources were considered in the RAC: (1) dispersion of the radionuclide in the air; (2) deposition on the RAC walls; and (3) deposition on the outer surface of the tested PPE or covering PPE preventing radioactive contamination. For the evaluation of the results, it was assumed that 90% of the total activity was dispersed in the air and that the surface activity of the RAC walls and PPE were equal. e equivalent dose was determined by calculation of the absorbed dose in the ORNL phantom organs. e deposited energy in each organ was initially obtained using the * F8-type tally independently for each of three radiation sources and both gamma and beta contributions. e deposited energies in each organ were then recalculated into the equivalent dose per unit activity. e equivalent doses were finally weighted by the tissue weighting factors defined in the ICRP 103 publication [11] and summed into the effective dose. e resulting calculated values of the whole body effective dose and equivalent doses on various organs were compared to the values of the same quantities, simulated in the same way for the ORNL phantom without the PPE. e effective dose on the human torso alone was also considered to compare individual whole-body PPE protecting against X-and gamma-ray and local ones. e following organs were included in the effective dose on the human torso calculation: lungs, stomach, colon, testes and genitalia, liver, oesophagus, urinary bladder, small intestine, gall bladder, pancreas, spleen, heart, adrenals, kidneys, and thymus. e decrease of equivalent dose on various organs, as well as whole-body effective dose decrease and decrease of effective dose on the human torso for individual PPE protecting against X-and gamma-ray, used in atmospheres of various dispersed radionuclides, were subsequently calculated from the resulting values of corresponding equivalent and effective doses. Figure 2 presents the spectra of the 133 Ba radionuclide gamma-ray without PPE and the penetrating BIORUBBER E-600 Vest PPE sample. e spectra were measured with an InSpector 1000 spectrometer with a detachable IPROL-1 scintillation LaBr 3 probe and smoothed by averaging over three adjacent channels. A significant decrease of relative attenuation of more energetic photons, penetrating the sample, is evident from the spectra.

Measurement of X-and Gamma-Ray Spectra.
Experimentally determined mean lead equivalents for individual PPE protecting against X-and gamma-ray, together with a reference PPE without a shielding layer and a reference lead sheet, are presented in Figure 3. e mean lead equivalent for the DEMRON IED RDD Shield was not determined due to a strong build-up factor in the thick material, inversely depending on penetrating photon energy.
From the mean lead equivalent values of tested PPE samples, it is evident that the higher the density thickness of a tested sample, the higher its lead equivalent ( Figure 3 and Table 1). e mean lead equivalent of some of the tested PPE protecting against X-and gamma-ray does not even meet the requirements of 0.35 mm, respectively, 0.25 mm, for the lead equivalent of heavy protective aprons, respectively, light protective aprons, used by radiological operators, respectively, used in operating rooms, and specified by CENELEC 1999 [12]. e lead equivalent of the reference OPCH-90 PPE (without any shielding layer) is almost negligible; the mean lead equivalent of the reference Pb sheet of 1.22 ± 0.10 mm corresponds to its thickness of 1.25 mm. e experimentally assessed mean lead equivalent value for HKX 1558 Whole-Body Anti-Radiation Wear equal to 0.24 ± 0.02 mm corresponds to the value of 0.25 mm stated by the manufacturer (Table 1). e experimentally determined lead equivalent for Df Vest W-1 mm equal to 0.99 ± 0.10 mm at the energy of 1,332.5 keV corresponds to the value of 1.0 mm stated by the manufacturer, while the same quantity for Df Vest W-2 mm of 1.71 ± 0.06 mm is 14.5% lower than the value of 2.0 mm stated by the manufacturer (Table 1). However, lead equivalent values determined at lower energies for both these PPE, as well as mean lead equivalents, are lower, which indicates the presence of a build-up factor in these relatively thick materials. Figure 4 presents the energy dependence of measured and simulated photon relative penetration in the BIORUBBER E-400 Vest and their relative difference. Both measured and simulated penetration rates are in excellent agreement, which proves the correctness of (1) the PPE material composition determined by XRF and SEM measurements and (2) the estimated density thickness of the material. e decreased relative photon penetration (and therefore increased attenuation) at the energy of about 88 keV corresponds to the lead absorption edge, which occurs at photoelectric absorption when there is sufficient photon energy to eject an electron from the K-shell.

Monte Carlo Simulations of PPE Material
Similar agreement between measured and simulated attenuation and penetration was obtained for all other studied materials as well. For the selected dispersed radioactive atmosphere, a decrease of energy deposition due to the presence of PPE protecting against X-and gamma-ray depends on the PPE lead equivalent. On the other hand, the higher the beta and gamma particle energy emitted by dispersed radionuclide, the lower the decrease of energy deposition, as higher energy particles are much less attenuated by PPE (Figure 2). Table 2 presents decrease of the various organs' contribution to the effective dose when protected with individual tested PPE exposed to the 131 I radionuclide dispersed in 10 m 3 of the atmosphere in the RAC geometry. Numerical results for other studied radionuclides are presented in the electronic annex. However, the results for other radionuclides are graphically presented in Figure 6, which summarises values of the effective dose decrease on human torso organs when protected with individual tested PPE exposed to various radionuclides in the given geometry.

Monte Carlo Simulations of Effective Dose
For individual simulated dispersed radionuclides, it is evident from Figure 6 that the higher the density thickness (and corresponding lead equivalent) of the PPE protecting against X-and gamma-ray, the higher the decrease of the effective dose. On the other hand, the higher the beta and gamma particle energy emitted by dispersed radionuclides, the lower the decrease of the effective dose.
For the simulated 99m Tc radionuclide, the decrease of the effective dose on the human torso organs of an ORNL phantom, protected by individual PPE protecting against Xand gamma-ray, is significantly higher than the resulting decrease when protected by the reference PPE OPCH-90 without a shielding layer. However, in the case of other simulated radionuclides, the decrease of the effective dose on human torso organs is only significantly higher than that of the reference PPE if the ORNL phantom is protected by PPE of a sufficient lead equivalent, which meets the CENELEC requirements for heavy and light aprons, used to shield against diagnostic medical X-ray radiation (Figures 6 and 3).
Most of the radiation-sensitive organs of the body are situated in the human torso, so the decrease of the whole-body

Conclusions
A collection of personal protective equipment protecting against X-and gamma-ray was gathered and tested at the National Institute for NBC Protection, Czech Republic. Relative penetration of X-and gamma-ray in tested samples in the energy range from 30. 5  Data Availability e measured spectra and simulated energy depositions in the ORNL phantom used to support the findings of this study are available from the corresponding author upon request. Visualisations of simulated energy depositions in the ORNL phantom are presented in the electronix annex.

Conflicts of Interest
e authors declare that there are no conflicts of interest regarding the publication of this paper.  Figure 6: Simulated decrease of effective dose on human torso organs when protected with tested PPE exposed to various radionuclides dispersed in the atmosphere.