Personal Dose Equivalent Conversion Coefficients Skins Dose for Mono-Energetic Photons, Electrons, and Positrons: Monte Carlo Approach and Development of an Analytical Approach

AbstractThe present study aims to calculate a new database of conversion coefficients from fluence and air Kerma to personal dose equivalent in two terms: absorbed dose and Kerma-approximations. In this work, we propose a new equation to perform an analytical fit of our Monte Carlo (MC) calculated conversion coefficients for photons for different angles. Also, we have calculated the conversion coefficients using the EGSnrc code. The conversion coefficients have been calculated for beams of monoenergetic photons from 0.015 to 10 MeV, incident on phantom ICRU for angles of incidence from 0° to a 75° in steps of 15°. Our computed values agree well when compared with those published for the ICRU 57 in Kerma-approximations with statistical uncertainties in the calculation around 2%. We can conclude from this work that the analytical approach is successful and powerful such as Monte Carlo methods to calculate the operational quantities.

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Tritons at energies of 10 MeV to 1 TeV: conversion coefficients for fluence-to-absorbed dose, equivalent dose, effective dose and gray equivalent, calculated using Monte Carlo radiation transport code MCNPX 2.7.C

Radiation Protection Dosimetry ◽

10.1093/rpd/ncq264 ◽

2010 ◽

Vol 142 (2-4) ◽

pp. 110-119 ◽

Cited By ~ 2

Author(s):

K. Copeland ◽

D. E. Parker ◽

W. Friedberg

Keyword(s):

Monte Carlo ◽

Effective Dose ◽

Radiation Transport ◽

Absorbed Dose ◽

Equivalent Dose ◽

Dose Equivalent ◽

Transport Code ◽

Conversion Coefficients

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Helions at energies of 10 MeV to 1 TeV: conversion coefficients for fluence-to-absorbed dose, equivalent dose, effective dose and gray equivalent, calculated using Monte Carlo radiation transport code MCNPX 2.7.C

Radiation Protection Dosimetry ◽

10.1093/rpd/ncq263 ◽

2010 ◽

Vol 142 (2-4) ◽

pp. 99-109 ◽

Cited By ~ 2

Author(s):

K. Copeland ◽

D. E. Parker ◽

W. Friedberg

Keyword(s):

Monte Carlo ◽

Effective Dose ◽

Radiation Transport ◽

Absorbed Dose ◽

Equivalent Dose ◽

Dose Equivalent ◽

Transport Code ◽

Conversion Coefficients

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Deuterons at energies of 10 MeV to 1 TeV: conversion coefficients for fluence-to-absorbed dose, equivalent dose, effective dose and gray equivalent, calculated using Monte Carlo radiation transport code MCNPX 2.7.C

Radiation Protection Dosimetry ◽

10.1093/rpd/ncq317 ◽

2010 ◽

Vol 143 (1) ◽

pp. 17-26 ◽

Cited By ~ 2

Author(s):

K. Copeland ◽

D. E. Parker ◽

W. Friedberg

Keyword(s):

Monte Carlo ◽

Effective Dose ◽

Radiation Transport ◽

Absorbed Dose ◽

Equivalent Dose ◽

Dose Equivalent ◽

Transport Code ◽

Conversion Coefficients

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Fluence to local skin absorbed dose and dose equivalent conversion coefficients for monoenergetic positrons using Monte-Carlo code MCNP6

Applied Radiation and Isotopes ◽

10.1016/j.apradiso.2015.11.029 ◽

2016 ◽

Vol 107 ◽

pp. 372-376 ◽

Cited By ~ 2

Author(s):

L. Bourgois ◽

R. Antoni

Keyword(s):

Monte Carlo ◽

Absorbed Dose ◽

Monte Carlo Code ◽

Dose Equivalent ◽

Local Skin ◽

Conversion Coefficients

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Calculation of X-ray spectra characteristics and kerma to personal dose equivalent Hp(10) conversion coefficients: Experimental approach and Monte Carlo modeling

Nuclear Engineering and Technology ◽

10.1016/j.net.2021.07.028 ◽

2021 ◽

Author(s):

A. Arectout ◽

I. Zidouh ◽

Y. Sadeq ◽

M. Azougagh ◽

B. Maroufi ◽

...

Keyword(s):

Monte Carlo ◽

Experimental Approach ◽

Dose Equivalent ◽

Monte Carlo Modeling ◽

X Ray ◽

Conversion Coefficients

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Neutron dose evaluation of Elekta Linac at two energies (10 & 18 MV) by MCNP code and comparison with experimental measurements

JOURNAL OF ADVANCES IN PHYSICS ◽

10.24297/jap.v6i1.1820 ◽

2014 ◽

Vol 6 (1) ◽

pp. 1006-1015

Author(s):

Negin Shagholi ◽

Hassan Ali ◽

Mahdi Sadeghi ◽

Arjang Shahvar ◽

Hoda Darestani ◽

...

Keyword(s):

Monte Carlo ◽

Measurement Data ◽

Calculated Data ◽

High Energy ◽

Neutron Dose ◽

Dose Assessment ◽

Photon Flux ◽

Dose Equivalent ◽

Monte Carlo Techniques ◽

Neutron Dose Equivalent

Medical linear accelerators, besides the clinically high energy electron and photon beams, produce other secondary particles such as neutrons which escalate the delivered dose. In this study the neutron dose at 10 and 18MV Elekta linac was obtained by using TLD600 and TLD700 as well as Monte Carlo simulation. For neutron dose assessment in 2020 cm2 field, TLDs were calibrated at first. Gamma calibration was performed with 10 and 18 MV linac and neutron calibration was done with 241Am-Be neutron source. For simulation, MCNPX code was used then calculated neutron dose equivalent was compared with measurement data. Neutron dose equivalent at 18 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 3.3, 4, 5 and 6 cm. Neutron dose at depths of less than 3.3cm was zero and maximized at the depth of 4 cm (44.39 mSvGy-1), whereas calculation resultedÂ in the maximum of 2.32 mSvGy-1 at the same depth. Neutron dose at 10 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 2.5, 3.3, 4 and 5 cm. No photoneutron dose was observed at depths of less than 3.3cm and the maximum was at 4cm equal to 5.44mSvGy-1, however, the calculated data showed the maximum of 0.077mSvGy-1 at the same depth. The comparison between measured photo neutron dose and calculated data along the beam axis in different depths, shows that the measurement data were much more than the calculated data, so it seems that TLD600 and TLD700 pairs are not suitable dosimeters for neutron dosimetry in linac central axis due to high photon flux, whereas MCNPX Monte Carlo techniques still remain a valuable tool for photonuclear dose studies.

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