Ilić, Radovan D.

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5a694057-8f12-4471-a780-788ea63a617e
  • Ilić, Radovan D. (9)
Projects

Author's Bibliography

Mathematical Simulation of the INR RAS SVZ-100 Neutron

Latysheva, L. N.; Sobolevsky, N. M.; Koptelov, E. A.; Ilić, Radovan D.

(2015)

TY  - JOUR
AU  - Latysheva, L. N.
AU  - Sobolevsky, N. M.
AU  - Koptelov, E. A.
AU  - Ilić, Radovan D.
PY  - 2015
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/2750
AB  - A mathematical model of the SVZ-100 lead slowing-down neutron spectrometer designed at the Institute for Nuclear Research, Russian Academy of Sciences (Moscow) is presented. The neutron spectra in the SVZ-100 measuring channels are calculated by the Monte Carlo method at different slowing-down times. The influence of the energy resolution of the spectrometer on the shape of the neutron cross sections is demonstrated. The developed model makes it possible to establish agreement between experimental data obtained using neutron spectrometers by different methods and with different resolutions and compare the results of measuring the neutron cross sections of thorium and transuranic elements using the SVZ-100 with recommended international databases.
T2  - Journal of Surface Investigation
T1  - Mathematical Simulation of the INR RAS SVZ-100 Neutron
VL  - 9
IS  - 6
SP  - 1126
EP  - 1129
DO  - 10.1134/S1027451015060142
ER  - 
@article{
author = "Latysheva, L. N. and Sobolevsky, N. M. and Koptelov, E. A. and Ilić, Radovan D.",
year = "2015",
abstract = "A mathematical model of the SVZ-100 lead slowing-down neutron spectrometer designed at the Institute for Nuclear Research, Russian Academy of Sciences (Moscow) is presented. The neutron spectra in the SVZ-100 measuring channels are calculated by the Monte Carlo method at different slowing-down times. The influence of the energy resolution of the spectrometer on the shape of the neutron cross sections is demonstrated. The developed model makes it possible to establish agreement between experimental data obtained using neutron spectrometers by different methods and with different resolutions and compare the results of measuring the neutron cross sections of thorium and transuranic elements using the SVZ-100 with recommended international databases.",
journal = "Journal of Surface Investigation",
title = "Mathematical Simulation of the INR RAS SVZ-100 Neutron",
volume = "9",
number = "6",
pages = "1126-1129",
doi = "10.1134/S1027451015060142"
}
Latysheva, L. N., Sobolevsky, N. M., Koptelov, E. A.,& Ilić, R. D.. (2015). Mathematical Simulation of the INR RAS SVZ-100 Neutron. in Journal of Surface Investigation, 9(6), 1126-1129.
https://doi.org/10.1134/S1027451015060142
Latysheva LN, Sobolevsky NM, Koptelov EA, Ilić RD. Mathematical Simulation of the INR RAS SVZ-100 Neutron. in Journal of Surface Investigation. 2015;9(6):1126-1129.
doi:10.1134/S1027451015060142 .
Latysheva, L. N., Sobolevsky, N. M., Koptelov, E. A., Ilić, Radovan D., "Mathematical Simulation of the INR RAS SVZ-100 Neutron" in Journal of Surface Investigation, 9, no. 6 (2015):1126-1129,
https://doi.org/10.1134/S1027451015060142 . .
2
1
2

Correlation Between Mosfet Dosimeter Energy Response and Its Shielding Material in Electron-Beam Radiation Environment

Stanković, Srboljub; Ilić, Radovan D.; Lazarević, Đorđe R.; Fetahovic, I.; Obrenović, Marija D.; Iricanin, B.

(2015)

TY  - CONF
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Lazarević, Đorđe R.
AU  - Fetahovic, I.
AU  - Obrenović, Marija D.
AU  - Iricanin, B.
PY  - 2015
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/7103
AB  - One of the most useful applications of MOSFET semiconductor components has been introduced to improve the gamma or electron radiation detection system. In many practical cases it is not easy to carry out experimental tests of semiconductor devices in radiation environment, so it is more convenient to perform the assessment of ionizing radiation interaction with semiconductor devices by using numerical methods based on Monte Carlo simulation techniques. A large number of previous studies have mainly focused on the study of MOSFET dosimeter response to gamma and X radiation fields. Therefore, this work will be focused on a new approach to the study radiation characteristics of the MOSFET dosimeter in fields of other types, such as field of high-energy electrons (4 MeV to 20 MeV). From the engineering point of view, it is important to consider the material that is used as a physical protection of the MOSFET dosimeter. So, it is important to investigate the energy dependence of MOSFET dosimeter to different shielding materials. For this purpose, special numerical experiments of electron transport within all layers of the elementary MOSFET structure will be performed. Shielding materials such as Kovar, Titanium Alloy with Aluminum and Niobium, Titanium Alloy with Zirconium and Niobium will be considered. The electron transport will be simulated with Monte Carlo method using the software package FOTELP-2K12. The distribution of deposited energy in all material zones of interest, as well as the absorbed dose in dosimeter sensitive zone of MOSFET structure will be determined by results obtained with numerical calculations. The physical shielding factor (PSF) for the MOSFET dosimeter, which can show the correlation between dosimeter energy dependence and shielding material in the field of electron beam radiation, will be determined within the paper. After comparing values of PSF for considered materials the recommendation for a lid material that serves as shielding for MOSFET dosimeter will be given.
T1  - Correlation Between Mosfet Dosimeter Energy Response and Its Shielding Material in Electron-Beam Radiation Environment
UR  - https://hdl.handle.net/21.15107/rcub_vinar_7103
ER  - 
@conference{
author = "Stanković, Srboljub and Ilić, Radovan D. and Lazarević, Đorđe R. and Fetahovic, I. and Obrenović, Marija D. and Iricanin, B.",
year = "2015",
abstract = "One of the most useful applications of MOSFET semiconductor components has been introduced to improve the gamma or electron radiation detection system. In many practical cases it is not easy to carry out experimental tests of semiconductor devices in radiation environment, so it is more convenient to perform the assessment of ionizing radiation interaction with semiconductor devices by using numerical methods based on Monte Carlo simulation techniques. A large number of previous studies have mainly focused on the study of MOSFET dosimeter response to gamma and X radiation fields. Therefore, this work will be focused on a new approach to the study radiation characteristics of the MOSFET dosimeter in fields of other types, such as field of high-energy electrons (4 MeV to 20 MeV). From the engineering point of view, it is important to consider the material that is used as a physical protection of the MOSFET dosimeter. So, it is important to investigate the energy dependence of MOSFET dosimeter to different shielding materials. For this purpose, special numerical experiments of electron transport within all layers of the elementary MOSFET structure will be performed. Shielding materials such as Kovar, Titanium Alloy with Aluminum and Niobium, Titanium Alloy with Zirconium and Niobium will be considered. The electron transport will be simulated with Monte Carlo method using the software package FOTELP-2K12. The distribution of deposited energy in all material zones of interest, as well as the absorbed dose in dosimeter sensitive zone of MOSFET structure will be determined by results obtained with numerical calculations. The physical shielding factor (PSF) for the MOSFET dosimeter, which can show the correlation between dosimeter energy dependence and shielding material in the field of electron beam radiation, will be determined within the paper. After comparing values of PSF for considered materials the recommendation for a lid material that serves as shielding for MOSFET dosimeter will be given.",
title = "Correlation Between Mosfet Dosimeter Energy Response and Its Shielding Material in Electron-Beam Radiation Environment",
url = "https://hdl.handle.net/21.15107/rcub_vinar_7103"
}
Stanković, S., Ilić, R. D., Lazarević, Đ. R., Fetahovic, I., Obrenović, M. D.,& Iricanin, B.. (2015). Correlation Between Mosfet Dosimeter Energy Response and Its Shielding Material in Electron-Beam Radiation Environment. .
https://hdl.handle.net/21.15107/rcub_vinar_7103
Stanković S, Ilić RD, Lazarević ĐR, Fetahovic I, Obrenović MD, Iricanin B. Correlation Between Mosfet Dosimeter Energy Response and Its Shielding Material in Electron-Beam Radiation Environment. 2015;.
https://hdl.handle.net/21.15107/rcub_vinar_7103 .
Stanković, Srboljub, Ilić, Radovan D., Lazarević, Đorđe R., Fetahovic, I., Obrenović, Marija D., Iricanin, B., "Correlation Between Mosfet Dosimeter Energy Response and Its Shielding Material in Electron-Beam Radiation Environment" (2015),
https://hdl.handle.net/21.15107/rcub_vinar_7103 .

Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant

Latysheva, L. N.; Bergman, A. A.; Sobolevsky, N. M.; Ilić, Radovan D.

(2013)

TY  - JOUR
AU  - Latysheva, L. N.
AU  - Bergman, A. A.
AU  - Sobolevsky, N. M.
AU  - Ilić, Radovan D.
PY  - 2013
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/5475
AB  - Lead slowing-down (LSD) spectrometers have a low energy resolution (about 30%), but their luminosity is 10(3) to 10(4) times higher than that of time-of-flight (TOF) spectrometers. A high luminosity of LSD spectrometers makes it possible to use them to measure neutron cross section for samples of mass about several micrograms. These features specify a niche for the application of LSD spectrometers in measuring neutron cross sections for elements hardly available in macroscopic amounts-in particular, for actinides. A mathematical simulation of the parameters of SVZ-100 LSD spectrometer of the Institute for Nuclear Research (INR, Moscow) is performed in the present study on the basis of the MCNPX code. It is found that the moderation constant, which is the main parameter of LSD spectrometers, is highly sensitive to the size and shape of detecting volumes in calculations and, hence, to the real size of experimental channels of the LSD spectrometer. DOI: 10.1134/S1063778813030113
T2  - Physics of Atomic Nuclei
T1  - Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant
VL  - 76
IS  - 4
SP  - 464
EP  - 468
DO  - 10.1134/S1063778813030113
ER  - 
@article{
author = "Latysheva, L. N. and Bergman, A. A. and Sobolevsky, N. M. and Ilić, Radovan D.",
year = "2013",
abstract = "Lead slowing-down (LSD) spectrometers have a low energy resolution (about 30%), but their luminosity is 10(3) to 10(4) times higher than that of time-of-flight (TOF) spectrometers. A high luminosity of LSD spectrometers makes it possible to use them to measure neutron cross section for samples of mass about several micrograms. These features specify a niche for the application of LSD spectrometers in measuring neutron cross sections for elements hardly available in macroscopic amounts-in particular, for actinides. A mathematical simulation of the parameters of SVZ-100 LSD spectrometer of the Institute for Nuclear Research (INR, Moscow) is performed in the present study on the basis of the MCNPX code. It is found that the moderation constant, which is the main parameter of LSD spectrometers, is highly sensitive to the size and shape of detecting volumes in calculations and, hence, to the real size of experimental channels of the LSD spectrometer. DOI: 10.1134/S1063778813030113",
journal = "Physics of Atomic Nuclei",
title = "Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant",
volume = "76",
number = "4",
pages = "464-468",
doi = "10.1134/S1063778813030113"
}
Latysheva, L. N., Bergman, A. A., Sobolevsky, N. M.,& Ilić, R. D.. (2013). Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant. in Physics of Atomic Nuclei, 76(4), 464-468.
https://doi.org/10.1134/S1063778813030113
Latysheva LN, Bergman AA, Sobolevsky NM, Ilić RD. Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant. in Physics of Atomic Nuclei. 2013;76(4):464-468.
doi:10.1134/S1063778813030113 .
Latysheva, L. N., Bergman, A. A., Sobolevsky, N. M., Ilić, Radovan D., "Effect of the size of experimental channels of the lead slowing-down spectrometer SVZ-100 (Institute for Nuclear Research, Moscow) on the moderation constant" in Physics of Atomic Nuclei, 76, no. 4 (2013):464-468,
https://doi.org/10.1134/S1063778813030113 . .
1
1
1

Monte Carlo Analysis of the Influence of Different Packaging on MOSFET Energy Response to X-rays and Gamma Radiation

Stanković, Srboljub; Ilić, Radovan D.; Živanović, Miloš Z.; Janković, Ksenija S.; Lončar, Boris B.

(2012)

TY  - JOUR
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Živanović, Miloš Z.
AU  - Janković, Ksenija S.
AU  - Lončar, Boris B.
PY  - 2012
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/5095
AB  - Radiation sensing MOSFETs have found numerous applications as detectors or device components in radiation fields used in nuclear industry, medical applications and space research. Monte Carlo simulations of MOSFET energy response to X-ray and gamma radiation for different packaging were performed. The photon transport Monte Carlo software FOTELP-2K10 has been adapted to obtain the energy deposited in MOSFET structure with microscopic dimensions. In this work the ratio between values of total energy deposited in the sensitive volume (thick SiO2 layer) for cases of MOSFET structure with and without package lid is presented. For this purpose is defined the shielding energy dependence factor (SDEF), and gave its value for kovar and Ti-24Al-11Nb and Ti-13Nb-13Zr alloys as lid materials.
T2  - Acta Physica Polonica A
T1  - Monte Carlo Analysis of the Influence of Different Packaging on MOSFET Energy Response to X-rays and Gamma Radiation
VL  - 122
IS  - 4
SP  - 655
EP  - 658
DO  - 10.12693/APhysPolA.122.655
ER  - 
@article{
author = "Stanković, Srboljub and Ilić, Radovan D. and Živanović, Miloš Z. and Janković, Ksenija S. and Lončar, Boris B.",
year = "2012",
abstract = "Radiation sensing MOSFETs have found numerous applications as detectors or device components in radiation fields used in nuclear industry, medical applications and space research. Monte Carlo simulations of MOSFET energy response to X-ray and gamma radiation for different packaging were performed. The photon transport Monte Carlo software FOTELP-2K10 has been adapted to obtain the energy deposited in MOSFET structure with microscopic dimensions. In this work the ratio between values of total energy deposited in the sensitive volume (thick SiO2 layer) for cases of MOSFET structure with and without package lid is presented. For this purpose is defined the shielding energy dependence factor (SDEF), and gave its value for kovar and Ti-24Al-11Nb and Ti-13Nb-13Zr alloys as lid materials.",
journal = "Acta Physica Polonica A",
title = "Monte Carlo Analysis of the Influence of Different Packaging on MOSFET Energy Response to X-rays and Gamma Radiation",
volume = "122",
number = "4",
pages = "655-658",
doi = "10.12693/APhysPolA.122.655"
}
Stanković, S., Ilić, R. D., Živanović, M. Z., Janković, K. S.,& Lončar, B. B.. (2012). Monte Carlo Analysis of the Influence of Different Packaging on MOSFET Energy Response to X-rays and Gamma Radiation. in Acta Physica Polonica A, 122(4), 655-658.
https://doi.org/10.12693/APhysPolA.122.655
Stanković S, Ilić RD, Živanović MZ, Janković KS, Lončar BB. Monte Carlo Analysis of the Influence of Different Packaging on MOSFET Energy Response to X-rays and Gamma Radiation. in Acta Physica Polonica A. 2012;122(4):655-658.
doi:10.12693/APhysPolA.122.655 .
Stanković, Srboljub, Ilić, Radovan D., Živanović, Miloš Z., Janković, Ksenija S., Lončar, Boris B., "Monte Carlo Analysis of the Influence of Different Packaging on MOSFET Energy Response to X-rays and Gamma Radiation" in Acta Physica Polonica A, 122, no. 4 (2012):655-658,
https://doi.org/10.12693/APhysPolA.122.655 . .
2
3
3

Characterization of New Structure for Silicon Carbide X-Ray Detector by Method Monte Carlo

Stanković, Srboljub; Ilić, Radovan D.; Janković, Ksenija S.; Vasić-Milovanović, Aleksandra; Lončar, Boris B.

(2011)

TY  - JOUR
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Janković, Ksenija S.
AU  - Vasić-Milovanović, Aleksandra
AU  - Lončar, Boris B.
PY  - 2011
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/6918
AB  - This work presents a characterization of radiation absorption properties of silicon carbide (SiC) as semiconductor for the realization of detectors for X-rays. SiC detectors can potentially reach superior performance with respect to all the other semiconductors presently employed in hazardous environments in nuclear and space science and technology. Physics and numerical modeling of photons transport through SiC detector is incorporated in non-destructive Monte Carlo method for determining the energy deposited and dose distribution. The Monte Carlo code has been adopted for numerical simulations for different detector conditions and configurations. The X-ray characterization of new SiC structures originates the improving of design of these detector systems.
T2  - Acta Physica Polonica A
T1  - Characterization of New Structure for Silicon Carbide X-Ray Detector by Method Monte Carlo
VL  - 120
IS  - 2
SP  - 252
EP  - 255
DO  - 10.12693/APhysPolA.120.252
ER  - 
@article{
author = "Stanković, Srboljub and Ilić, Radovan D. and Janković, Ksenija S. and Vasić-Milovanović, Aleksandra and Lončar, Boris B.",
year = "2011",
abstract = "This work presents a characterization of radiation absorption properties of silicon carbide (SiC) as semiconductor for the realization of detectors for X-rays. SiC detectors can potentially reach superior performance with respect to all the other semiconductors presently employed in hazardous environments in nuclear and space science and technology. Physics and numerical modeling of photons transport through SiC detector is incorporated in non-destructive Monte Carlo method for determining the energy deposited and dose distribution. The Monte Carlo code has been adopted for numerical simulations for different detector conditions and configurations. The X-ray characterization of new SiC structures originates the improving of design of these detector systems.",
journal = "Acta Physica Polonica A",
title = "Characterization of New Structure for Silicon Carbide X-Ray Detector by Method Monte Carlo",
volume = "120",
number = "2",
pages = "252-255",
doi = "10.12693/APhysPolA.120.252"
}
Stanković, S., Ilić, R. D., Janković, K. S., Vasić-Milovanović, A.,& Lončar, B. B.. (2011). Characterization of New Structure for Silicon Carbide X-Ray Detector by Method Monte Carlo. in Acta Physica Polonica A, 120(2), 252-255.
https://doi.org/10.12693/APhysPolA.120.252
Stanković S, Ilić RD, Janković KS, Vasić-Milovanović A, Lončar BB. Characterization of New Structure for Silicon Carbide X-Ray Detector by Method Monte Carlo. in Acta Physica Polonica A. 2011;120(2):252-255.
doi:10.12693/APhysPolA.120.252 .
Stanković, Srboljub, Ilić, Radovan D., Janković, Ksenija S., Vasić-Milovanović, Aleksandra, Lončar, Boris B., "Characterization of New Structure for Silicon Carbide X-Ray Detector by Method Monte Carlo" in Acta Physica Polonica A, 120, no. 2 (2011):252-255,
https://doi.org/10.12693/APhysPolA.120.252 . .
2
2
2

Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials

Stanković, Srboljub; Ilić, Radovan D.; Janković, Ksenija S.; Bojović, D.; Lončar, Boris B.

(2010)

TY  - JOUR
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Janković, Ksenija S.
AU  - Bojović, D.
AU  - Lončar, Boris B.
PY  - 2010
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/6871
AB  - Nuclear facilities as nuclear power stations, nuclear research reactors, particle accelerators and linear accelerator in medical institution using concrete in building construction. The different type materials of the aggregate as component of concrete were analyzed to provide radiation protection. The energy deposited the transmission factor and the mass attenuation coefficients in ordinary and barite concretes have been calculated with the photon transport Monte Carlo software. The numerical simulations results show that using barite as an aggregate in the concrete is one of the solutions for gamma ray shielding. Thereat, it is shown non-destructive method for determining the gamma radiation absorption characteristics of concrete.
T2  - Acta Physica Polonica A
T1  - Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials
VL  - 117
IS  - 5
SP  - 812
EP  - 816
DO  - 10.12693/APhysPolA.117.812
ER  - 
@article{
author = "Stanković, Srboljub and Ilić, Radovan D. and Janković, Ksenija S. and Bojović, D. and Lončar, Boris B.",
year = "2010",
abstract = "Nuclear facilities as nuclear power stations, nuclear research reactors, particle accelerators and linear accelerator in medical institution using concrete in building construction. The different type materials of the aggregate as component of concrete were analyzed to provide radiation protection. The energy deposited the transmission factor and the mass attenuation coefficients in ordinary and barite concretes have been calculated with the photon transport Monte Carlo software. The numerical simulations results show that using barite as an aggregate in the concrete is one of the solutions for gamma ray shielding. Thereat, it is shown non-destructive method for determining the gamma radiation absorption characteristics of concrete.",
journal = "Acta Physica Polonica A",
title = "Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials",
volume = "117",
number = "5",
pages = "812-816",
doi = "10.12693/APhysPolA.117.812"
}
Stanković, S., Ilić, R. D., Janković, K. S., Bojović, D.,& Lončar, B. B.. (2010). Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials. in Acta Physica Polonica A, 117(5), 812-816.
https://doi.org/10.12693/APhysPolA.117.812
Stanković S, Ilić RD, Janković KS, Bojović D, Lončar BB. Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials. in Acta Physica Polonica A. 2010;117(5):812-816.
doi:10.12693/APhysPolA.117.812 .
Stanković, Srboljub, Ilić, Radovan D., Janković, Ksenija S., Bojović, D., Lončar, Boris B., "Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials" in Acta Physica Polonica A, 117, no. 5 (2010):812-816,
https://doi.org/10.12693/APhysPolA.117.812 . .
38
29
37

Radiation Absorption Characteristics of Titanium Alloys

Stanković, Srboljub; Ilić, Radovan D.; Davidović, Dragomir M.; Petrović, Milica S.; Tadić, Srđan; Kovačević, Milojko

(2009)

TY  - JOUR
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Davidović, Dragomir M.
AU  - Petrović, Milica S.
AU  - Tadić, Srđan
AU  - Kovačević, Milojko
PY  - 2009
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/6798
AB  - Titanium alloys have found numerous applications in space research, and nuclear industry and research. Since X-rays constitute an important part of the space radiation environment, numerical simulations of radiation absorption characteristics of titanium alloys were studied in this paper. The photon transport Monte Carlo software was used for determining the energy deposited in titanium samples. The numerical results show the pronounced dependence of radiation absorption properties of different combinations of components in alloy. The results obtained are encouraging in respect of optimization of structure of alloys regarding their required features in radiation shielding.
T2  - Acta Physica Polonica A
T1  - Radiation Absorption Characteristics of Titanium Alloys
VL  - 115
IS  - 4
SP  - 820
EP  - 822
DO  - 10.12693/APhysPolA.115.820
ER  - 
@article{
author = "Stanković, Srboljub and Ilić, Radovan D. and Davidović, Dragomir M. and Petrović, Milica S. and Tadić, Srđan and Kovačević, Milojko",
year = "2009",
abstract = "Titanium alloys have found numerous applications in space research, and nuclear industry and research. Since X-rays constitute an important part of the space radiation environment, numerical simulations of radiation absorption characteristics of titanium alloys were studied in this paper. The photon transport Monte Carlo software was used for determining the energy deposited in titanium samples. The numerical results show the pronounced dependence of radiation absorption properties of different combinations of components in alloy. The results obtained are encouraging in respect of optimization of structure of alloys regarding their required features in radiation shielding.",
journal = "Acta Physica Polonica A",
title = "Radiation Absorption Characteristics of Titanium Alloys",
volume = "115",
number = "4",
pages = "820-822",
doi = "10.12693/APhysPolA.115.820"
}
Stanković, S., Ilić, R. D., Davidović, D. M., Petrović, M. S., Tadić, S.,& Kovačević, M.. (2009). Radiation Absorption Characteristics of Titanium Alloys. in Acta Physica Polonica A, 115(4), 820-822.
https://doi.org/10.12693/APhysPolA.115.820
Stanković S, Ilić RD, Davidović DM, Petrović MS, Tadić S, Kovačević M. Radiation Absorption Characteristics of Titanium Alloys. in Acta Physica Polonica A. 2009;115(4):820-822.
doi:10.12693/APhysPolA.115.820 .
Stanković, Srboljub, Ilić, Radovan D., Davidović, Dragomir M., Petrović, Milica S., Tadić, Srđan, Kovačević, Milojko, "Radiation Absorption Characteristics of Titanium Alloys" in Acta Physica Polonica A, 115, no. 4 (2009):820-822,
https://doi.org/10.12693/APhysPolA.115.820 . .
2
2

Characterization of X-Ray Diamond Detector by Monte Carlo Method

Stanković, Srboljub; Ilić, Radovan D.; Davidović, Dragomir M.; Petrović, Milica S.

(2009)

TY  - JOUR
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Davidović, Dragomir M.
AU  - Petrović, Milica S.
PY  - 2009
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/6797
AB  - The use of diamond as material for X-ray detector is subject of investigation and practice in radiotherapy, space and material science and technology. This paper presents the results of application of Monte Carlo method for simulation of photon transport through diamond detector. The aim is restitution and demonstrating of numerical technique for characterization of electrical properties for different detector conditions and configurations. Monte Carlo code was adopted to determine the energy deposited and dose distribution in the structure of diamond detector. Our results show that the use of numerical simulations may be of essential help in design of diamond detector systems.
T2  - Acta Physica Polonica A
T1  - Characterization of X-Ray Diamond Detector by Monte Carlo Method
VL  - 115
IS  - 4
SP  - 816
EP  - 819
DO  - 10.12693/APhysPolA.115.816
ER  - 
@article{
author = "Stanković, Srboljub and Ilić, Radovan D. and Davidović, Dragomir M. and Petrović, Milica S.",
year = "2009",
abstract = "The use of diamond as material for X-ray detector is subject of investigation and practice in radiotherapy, space and material science and technology. This paper presents the results of application of Monte Carlo method for simulation of photon transport through diamond detector. The aim is restitution and demonstrating of numerical technique for characterization of electrical properties for different detector conditions and configurations. Monte Carlo code was adopted to determine the energy deposited and dose distribution in the structure of diamond detector. Our results show that the use of numerical simulations may be of essential help in design of diamond detector systems.",
journal = "Acta Physica Polonica A",
title = "Characterization of X-Ray Diamond Detector by Monte Carlo Method",
volume = "115",
number = "4",
pages = "816-819",
doi = "10.12693/APhysPolA.115.816"
}
Stanković, S., Ilić, R. D., Davidović, D. M.,& Petrović, M. S.. (2009). Characterization of X-Ray Diamond Detector by Monte Carlo Method. in Acta Physica Polonica A, 115(4), 816-819.
https://doi.org/10.12693/APhysPolA.115.816
Stanković S, Ilić RD, Davidović DM, Petrović MS. Characterization of X-Ray Diamond Detector by Monte Carlo Method. in Acta Physica Polonica A. 2009;115(4):816-819.
doi:10.12693/APhysPolA.115.816 .
Stanković, Srboljub, Ilić, Radovan D., Davidović, Dragomir M., Petrović, Milica S., "Characterization of X-Ray Diamond Detector by Monte Carlo Method" in Acta Physica Polonica A, 115, no. 4 (2009):816-819,
https://doi.org/10.12693/APhysPolA.115.816 . .
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Radiological characterization of semiconductor materials in field effect transistor dosimeter by Monte Carlo method

Stanković, Srboljub; Ilić, Radovan D.; Petrović, Milica S.; Lončar, Boris B.; Vasić, Aleksandra

(2006)

TY  - JOUR
AU  - Stanković, Srboljub
AU  - Ilić, Radovan D.
AU  - Petrović, Milica S.
AU  - Lončar, Boris B.
AU  - Vasić, Aleksandra
PY  - 2006
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/6612
AB  - The use of semiconductor materials in radiation processing, radiation therapy and diagnostics, and detection of cosmic radiation motivated development of numerical methods for its radiological characterization. This paper presents the application of the Monte Carlo method using the FOTELP-2K4 code for radiological characterization of Metal Oxide Semiconductor Field Effect Transistor (MOSFET) dosimeter. The advantages of MOSFET dosimeters include small size, immediate readout, and ease of use for a wide photon energy range. In order to determine the dosimeter response accurately, distribution of the absorbed dose in the MOSFET structure has been investigated. Our results show that the absorbed dose distribution calculated by the presented simulation model compares well with the published data.
T2  - Materials Science Forum
T1  - Radiological characterization of semiconductor materials in field effect transistor dosimeter by Monte Carlo method
VL  - 518
SP  - 361
EP  - 365
DO  - 10.4028/www.scientific.net/MSF.518.361
ER  - 
@article{
author = "Stanković, Srboljub and Ilić, Radovan D. and Petrović, Milica S. and Lončar, Boris B. and Vasić, Aleksandra",
year = "2006",
abstract = "The use of semiconductor materials in radiation processing, radiation therapy and diagnostics, and detection of cosmic radiation motivated development of numerical methods for its radiological characterization. This paper presents the application of the Monte Carlo method using the FOTELP-2K4 code for radiological characterization of Metal Oxide Semiconductor Field Effect Transistor (MOSFET) dosimeter. The advantages of MOSFET dosimeters include small size, immediate readout, and ease of use for a wide photon energy range. In order to determine the dosimeter response accurately, distribution of the absorbed dose in the MOSFET structure has been investigated. Our results show that the absorbed dose distribution calculated by the presented simulation model compares well with the published data.",
journal = "Materials Science Forum",
title = "Radiological characterization of semiconductor materials in field effect transistor dosimeter by Monte Carlo method",
volume = "518",
pages = "361-365",
doi = "10.4028/www.scientific.net/MSF.518.361"
}
Stanković, S., Ilić, R. D., Petrović, M. S., Lončar, B. B.,& Vasić, A.. (2006). Radiological characterization of semiconductor materials in field effect transistor dosimeter by Monte Carlo method. in Materials Science Forum, 518, 361-365.
https://doi.org/10.4028/www.scientific.net/MSF.518.361
Stanković S, Ilić RD, Petrović MS, Lončar BB, Vasić A. Radiological characterization of semiconductor materials in field effect transistor dosimeter by Monte Carlo method. in Materials Science Forum. 2006;518:361-365.
doi:10.4028/www.scientific.net/MSF.518.361 .
Stanković, Srboljub, Ilić, Radovan D., Petrović, Milica S., Lončar, Boris B., Vasić, Aleksandra, "Radiological characterization of semiconductor materials in field effect transistor dosimeter by Monte Carlo method" in Materials Science Forum, 518 (2006):361-365,
https://doi.org/10.4028/www.scientific.net/MSF.518.361 . .
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