TY  - CONF
AU  - Stanković, Srboljub
AU  - Ilić, Radovan
AU  - Marinković, Predrag
AU  - Nikolić, Dragana
AU  - Kržanović, Nikola
AU  - Radenković, Mirjana
PY  - 2019
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12139
AB  - During the construction of nuclear facilities, radiotherapy centers, hospitals with radiological diagnostic facilities, and radioactive waste storage facilities, complex requirements for protection against ionizing radiation have been set up. In its basic principles, modern approaches in the design of radiation protection procedures were derived from empirical conclusions that were obtained by solving practical problems encountered by nuclear engineers and physicists. In the radiation protection projections, as well as in the formation of different technical and technological procedures in the radiation environment, one of the most important characteristics is the build-up factor of the material used. Based on experimental and theoretical research, empirical formulas for calculating the build-up factors are used to solve practical problems in radiation protection. With the development of information and computer technologies for calculating the build-up factor, other numerical methods are also used, of which a very attractive and efficient Monte Carlo calculation method is used. In this paper, the calculations with the empirical approximate formulas by Taylor and Berger, as well as the results obtained by using the software based on the Monte Carlo method, were used to determine the build-up of the factors in the protection of gamma and X radiation for several selected materials (lead, water, iron, etc.). By comparing the results obtained with the empirical approximations and Monte Carlo calculations, certain conclusions have been drawn that direct us to new critical considerations about the usefulness of using the chosen method of calculation for the build-up factor of materials found in modern technological processes using sources of gamma and X radiation.
PB  - Niš : Sievert Association
C3  - RAP 2019 : International conference on radiation applications : Book of abstracts
T1  - Application of the Monte Carlo method and the empirical approximate formulas by Taylor and Berger for the calculation of the build-up factor in the fields of gamma and X radiation
SP  - 93
EP  - 93
UR  - https://hdl.handle.net/21.15107/rcub_vinar_12139
ER  - 

@conference{
author = "Stanković, Srboljub and Ilić, Radovan and Marinković, Predrag and Nikolić, Dragana and Kržanović, Nikola and Radenković, Mirjana",
year = "2019",
abstract = "During the construction of nuclear facilities, radiotherapy centers, hospitals with radiological diagnostic facilities, and radioactive waste storage facilities, complex requirements for protection against ionizing radiation have been set up. In its basic principles, modern approaches in the design of radiation protection procedures were derived from empirical conclusions that were obtained by solving practical problems encountered by nuclear engineers and physicists. In the radiation protection projections, as well as in the formation of different technical and technological procedures in the radiation environment, one of the most important characteristics is the build-up factor of the material used. Based on experimental and theoretical research, empirical formulas for calculating the build-up factors are used to solve practical problems in radiation protection. With the development of information and computer technologies for calculating the build-up factor, other numerical methods are also used, of which a very attractive and efficient Monte Carlo calculation method is used. In this paper, the calculations with the empirical approximate formulas by Taylor and Berger, as well as the results obtained by using the software based on the Monte Carlo method, were used to determine the build-up of the factors in the protection of gamma and X radiation for several selected materials (lead, water, iron, etc.). By comparing the results obtained with the empirical approximations and Monte Carlo calculations, certain conclusions have been drawn that direct us to new critical considerations about the usefulness of using the chosen method of calculation for the build-up factor of materials found in modern technological processes using sources of gamma and X radiation.",
publisher = "Niš : Sievert Association",
journal = "RAP 2019 : International conference on radiation applications : Book of abstracts",
title = "Application of the Monte Carlo method and the empirical approximate formulas by Taylor and Berger for the calculation of the build-up factor in the fields of gamma and X radiation",
pages = "93-93",
url = "https://hdl.handle.net/21.15107/rcub_vinar_12139"
}

Stanković, S., Ilić, R., Marinković, P., Nikolić, D., Kržanović, N.,& Radenković, M.. (2019). Application of the Monte Carlo method and the empirical approximate formulas by Taylor and Berger for the calculation of the build-up factor in the fields of gamma and X radiation. in RAP 2019 : International conference on radiation applications : Book of abstracts
Niš : Sievert Association., 93-93.
https://hdl.handle.net/21.15107/rcub_vinar_12139

Stanković S, Ilić R, Marinković P, Nikolić D, Kržanović N, Radenković M. Application of the Monte Carlo method and the empirical approximate formulas by Taylor and Berger for the calculation of the build-up factor in the fields of gamma and X radiation. in RAP 2019 : International conference on radiation applications : Book of abstracts. 2019;:93-93.
https://hdl.handle.net/21.15107/rcub_vinar_12139 .

Stanković, Srboljub, Ilić, Radovan, Marinković, Predrag, Nikolić, Dragana, Kržanović, Nikola, Radenković, Mirjana, "Application of the Monte Carlo method and the empirical approximate formulas by Taylor and Berger for the calculation of the build-up factor in the fields of gamma and X radiation" in RAP 2019 : International conference on radiation applications : Book of abstracts (2019):93-93,
https://hdl.handle.net/21.15107/rcub_vinar_12139 .

TY  - CONF
AU  - Krstić, Dragana Ž.
AU  - Ilić, Radovan
AU  - Jovanović, Aleksandra
AU  - Nikezić, Dragoslav
AU  - Jeremić, Marija
AU  - Nikolić, Nebojša
AU  - Mihajlović, Jasmina
PY  - 2019
UR  - https://plus.sr.cobiss.net/opac7/bib/279687436
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/8719
AB  - U radu je prikazano poređenje apsorbovanih doza u brahiterapijskim planovima i Monte Karlo simulacijama u brahiterapiji pacijentkinja sa karcinomom grlića materice. U Odeljenju za brahiterapiju u Kliničkom centru Kragujevac primenjuje se mikroSelektron za intrakavitarnu brahiterapiju u HDR režimu. Ovaj uređaj koristi minijaturni radioaktivni izvor 192Ir u obliku cilindra, aktivnih dimenzija 0,6 mm × 3,5 mm, i visoke početne aktivnosti od 370 GBq.Pre terapije, vrši se kompjutersko planiranje, koje predstavlja kompjutersku rekonstruk-ciju položaja vodiča izvora u pacijentu na osnovu dva radiografska snimka, i izodozno planiranje u odnosu na željene dozimetrijske tačke. Osnovni podaci planiranja su dnevna doza, koja iznosi 700 cGy i broj frakcija; dnevna doza se isporučuje se u tri frakcije jednom nedeljno. Monte Karlo simulacije su obavljene korišćenjem MCNP6 softvera verzije 2.0 kako bi se procenila raspodela doze u materici i kritičnim organima od rizika (bešika i debelo crevo). MCNP F6 tally (MeV/g) je izabran zbog lakog konvertovanja deponovane energije u apsorbovanu dozu. Za pripremu ulaznih datoteka koje simuliraju brahi-terapiju korišćeni su matematički ORNL i voksel fantomi. Upoređivanjem izmerenih i izračunatih vrednosti može se videti da su Monte Carlo tehnike moćno sredstvo za primenu u planiranju brahiterapije.
AB  - This paper presents the comparison of absorbed doses in brachytherapy plans and Monte Carlo simulation for brachytherapy treatment of a female patient with cervix carcinoma. At the Department of Brachytherapy at the Clinical Center Kragujevac, the microSelectron after loading deviceis used for intracavitary brachytherapy in the HDR regime. This device uses a miniature radioactive source 192Ir in the form of a cylinder, active dimensions of 0.6 mm × 3.5 mm, and a high initial activity of about 370 GBq. Before therapy, computer planning is performed, which represents a computer reconstruction of the position of the source guide in the patient based on two radiographic images, and isodose planning in relation to the desired dosimetry points. Essential planning data are the daily dose and number of fractions. In this case, the daily dose is 700 cGy and is delivered in three fractions once a week. This means that the duration of this brachytherapy treatment will be a total of three weeks. Monte Carlo simulations by using MCNP6 code version 2.0 were applied for brachytherapy treatment to estimate the dose distribution in uterus and several critical organs at risk (bladder and colon). The MCNP tally f6 (MeV/g) was chosen due to easy convert energy deposition toabsorbed dose. The computational ORNL and voxel phantoms were used to prepare input files which simulate brachytherapy.By comparing measured and calculated values, it can be seen that Monte Carlo techniques are a powerful tool for application in brachytherapy planning.
PB  - Београд : Институт за нуклеарне науке "Винча" : Друштво за заштиту од зрачења Србије и Црне Горе
C3  - 30. симпозијум ДЗЗСЦГ : зборник радова
T1  - Monte Carlo dozimetrija u brahiterapiji kancera cerviksa
T1  - Monte Carlo dosimetry for brachytherapy of cervical cancer
SP  - 483
EP  - 488
UR  - https://hdl.handle.net/21.15107/rcub_vinar_8719
ER  - 

@conference{
author = "Krstić, Dragana Ž. and Ilić, Radovan and Jovanović, Aleksandra and Nikezić, Dragoslav and Jeremić, Marija and Nikolić, Nebojša and Mihajlović, Jasmina",
year = "2019",
abstract = "U radu je prikazano poređenje apsorbovanih doza u brahiterapijskim planovima i Monte Karlo simulacijama u brahiterapiji pacijentkinja sa karcinomom grlića materice. U Odeljenju za brahiterapiju u Kliničkom centru Kragujevac primenjuje se mikroSelektron za intrakavitarnu brahiterapiju u HDR režimu. Ovaj uređaj koristi minijaturni radioaktivni izvor 192Ir u obliku cilindra, aktivnih dimenzija 0,6 mm × 3,5 mm, i visoke početne aktivnosti od 370 GBq.Pre terapije, vrši se kompjutersko planiranje, koje predstavlja kompjutersku rekonstruk-ciju položaja vodiča izvora u pacijentu na osnovu dva radiografska snimka, i izodozno planiranje u odnosu na željene dozimetrijske tačke. Osnovni podaci planiranja su dnevna doza, koja iznosi 700 cGy i broj frakcija; dnevna doza se isporučuje se u tri frakcije jednom nedeljno. Monte Karlo simulacije su obavljene korišćenjem MCNP6 softvera verzije 2.0 kako bi se procenila raspodela doze u materici i kritičnim organima od rizika (bešika i debelo crevo). MCNP F6 tally (MeV/g) je izabran zbog lakog konvertovanja deponovane energije u apsorbovanu dozu. Za pripremu ulaznih datoteka koje simuliraju brahi-terapiju korišćeni su matematički ORNL i voksel fantomi. Upoređivanjem izmerenih i izračunatih vrednosti može se videti da su Monte Carlo tehnike moćno sredstvo za primenu u planiranju brahiterapije., This paper presents the comparison of absorbed doses in brachytherapy plans and Monte Carlo simulation for brachytherapy treatment of a female patient with cervix carcinoma. At the Department of Brachytherapy at the Clinical Center Kragujevac, the microSelectron after loading deviceis used for intracavitary brachytherapy in the HDR regime. This device uses a miniature radioactive source 192Ir in the form of a cylinder, active dimensions of 0.6 mm × 3.5 mm, and a high initial activity of about 370 GBq. Before therapy, computer planning is performed, which represents a computer reconstruction of the position of the source guide in the patient based on two radiographic images, and isodose planning in relation to the desired dosimetry points. Essential planning data are the daily dose and number of fractions. In this case, the daily dose is 700 cGy and is delivered in three fractions once a week. This means that the duration of this brachytherapy treatment will be a total of three weeks. Monte Carlo simulations by using MCNP6 code version 2.0 were applied for brachytherapy treatment to estimate the dose distribution in uterus and several critical organs at risk (bladder and colon). The MCNP tally f6 (MeV/g) was chosen due to easy convert energy deposition toabsorbed dose. The computational ORNL and voxel phantoms were used to prepare input files which simulate brachytherapy.By comparing measured and calculated values, it can be seen that Monte Carlo techniques are a powerful tool for application in brachytherapy planning.",
publisher = "Београд : Институт за нуклеарне науке "Винча" : Друштво за заштиту од зрачења Србије и Црне Горе",
journal = "30. симпозијум ДЗЗСЦГ : зборник радова",
title = "Monte Carlo dozimetrija u brahiterapiji kancera cerviksa, Monte Carlo dosimetry for brachytherapy of cervical cancer",
pages = "483-488",
url = "https://hdl.handle.net/21.15107/rcub_vinar_8719"
}

Krstić, D. Ž., Ilić, R., Jovanović, A., Nikezić, D., Jeremić, M., Nikolić, N.,& Mihajlović, J.. (2019). Monte Carlo dozimetrija u brahiterapiji kancera cerviksa. in 30. симпозијум ДЗЗСЦГ : зборник радова
Београд : Институт за нуклеарне науке "Винча" : Друштво за заштиту од зрачења Србије и Црне Горе., 483-488.
https://hdl.handle.net/21.15107/rcub_vinar_8719

Krstić DŽ, Ilić R, Jovanović A, Nikezić D, Jeremić M, Nikolić N, Mihajlović J. Monte Carlo dozimetrija u brahiterapiji kancera cerviksa. in 30. симпозијум ДЗЗСЦГ : зборник радова. 2019;:483-488.
https://hdl.handle.net/21.15107/rcub_vinar_8719 .

Krstić, Dragana Ž., Ilić, Radovan, Jovanović, Aleksandra, Nikezić, Dragoslav, Jeremić, Marija, Nikolić, Nebojša, Mihajlović, Jasmina, "Monte Carlo dozimetrija u brahiterapiji kancera cerviksa" in 30. симпозијум ДЗЗСЦГ : зборник радова (2019):483-488,
https://hdl.handle.net/21.15107/rcub_vinar_8719 .

TY  - CONF
AU  - Stanković, Srboljub
AU  - Ilić, Radovan
AU  - Lazare, Đ.
AU  - Fetahović, I.
AU  - Obrenović, M.
AU  - Iričanin, B.
PY  - 2015
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12147
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.
PB  - IEEE : Institute of Electrical and Electronics Engineers
C3  - PPC 2015 : Pulsed Power Conference : Proceedings book
T1  - Correlation between MOSFET dosimeter energy respon and its shelding material in electron-beam radiation environment
SP  - 1
EP  - 5
DO  - 10.1109/PPC.2015.7296888
ER  - 

@conference{
author = "Stanković, Srboljub and Ilić, Radovan and Lazare, Đ. and Fetahović, I. and Obrenović, M. and Iričanin, 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.",
publisher = "IEEE : Institute of Electrical and Electronics Engineers",
journal = "PPC 2015 : Pulsed Power Conference : Proceedings book",
title = "Correlation between MOSFET dosimeter energy respon and its shelding material in electron-beam radiation environment",
pages = "1-5",
doi = "10.1109/PPC.2015.7296888"
}

Stanković, S., Ilić, R., Lazare, Đ., Fetahović, I., Obrenović, M.,& Iričanin, B.. (2015). Correlation between MOSFET dosimeter energy respon and its shelding material in electron-beam radiation environment. in PPC 2015 : Pulsed Power Conference : Proceedings book
IEEE : Institute of Electrical and Electronics Engineers., 1-5.
https://doi.org/10.1109/PPC.2015.7296888

Stanković S, Ilić R, Lazare Đ, Fetahović I, Obrenović M, Iričanin B. Correlation between MOSFET dosimeter energy respon and its shelding material in electron-beam radiation environment. in PPC 2015 : Pulsed Power Conference : Proceedings book. 2015;:1-5.
doi:10.1109/PPC.2015.7296888 .

Stanković, Srboljub, Ilić, Radovan, Lazare, Đ., Fetahović, I., Obrenović, M., Iričanin, B., "Correlation between MOSFET dosimeter energy respon and its shelding material in electron-beam radiation environment" in PPC 2015 : Pulsed Power Conference : Proceedings book (2015):1-5,
https://doi.org/10.1109/PPC.2015.7296888 . .

TY  - CONF
AU  - Stanković, Srboljub
AU  - Jakšić, Aleksandar
AU  - Ilić, Radovan
AU  - Nikolić, Dragana
AU  - Lončar, Boris
AU  - Lazarević, Đorđe
AU  - Karadžić, Katarina
PY  - 2015
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12151
AB  - MOSFET electronic components are already the subject of several decades of research in various fields of dosimetry and radiation protection. Special interest appeared when these components are started to be used as dosimeters in radiotherapy with electron beams. However, if one looks much more serious in the wider scientific research horizon, all the results obtained in experiments with precisely defined energies of incident electrons can be used in other disciplines which consider the impacts spectra of cosmic radiation on electronic devices, which is especially importance for cosmic science and space research instrumentation. In this paper, one of the objectives was to examine the electrical characteristics specially designed ESAPMOS RADFET dosimeters in the experiments that were conducted on a linear accelerator installations. RADFET components are bombarded electron beams energy of 6 MeV and 8 MeV, and then are followed by changes in threshold voltage shift mean values depending on the change of absorbed dose is referred to as D(cGy) was determined in water. Conclusions performance RADFET components are more than encouraging in terms of further research to improve the linearity of the energy dependence as widely energy electrons. In the second part of the test complex structure of packaging components RADFET focus is placed on the determination of the energy deposited in layers that are of interest for the analysis of microscopic processes related to the recombination of radiation-induced electron-hole pairs. Transport incident electrons through all the layers of structure RADFET component type ESAPMOS was carried out numerical simulations of the Monte Carlo method using the software package FOTELP-2K12. On this occasion, were taken into account all the physical processes of interaction of electrons with materials given structure. When he conquered the numerical application of mathematical and physical model for determining the value of the absorbed energy as the energy deposited per unit mass in a given layers with different materials, it could be accessed defining physical shielding factor (PSF) for a given structure RADFET components. Physical shielding factor (PSF) is defined as the ratio of absorbed dose values, which in fact means that it is equal to the energy deposited when the RADFET is shielded with protection, and the RADFET without lid. When we know the energy dependence factor for PSF of RADFET with and without armour, can be carried out and the analysis of whether and to what extent the energy required compensating the electronic components. Monte Carlo simulations were performed for the transport of incident electrons from 4 MeV, 6 MeV, 8 MeV and 12 MeV. It can be concluded that the different energy of incident electrons there is a significant influence of material Kovar on the absorbed energy in SiO2 and Si layers structure RADFET, in cases where Kovar used among other things as physical protection.
PB  - Niš : RAD Association
C3  - RAD 2015 : International Conference on Radiation and Applications in Various Fields of Research : Book of abstracts
T1  - Experiments with RADFET dosimeter in electron-beams irradiation and numerical computation of the physical shielding factor
SP  - 153
EP  - 153
UR  - https://hdl.handle.net/21.15107/rcub_vinar_12151
ER  - 

@conference{
author = "Stanković, Srboljub and Jakšić, Aleksandar and Ilić, Radovan and Nikolić, Dragana and Lončar, Boris and Lazarević, Đorđe and Karadžić, Katarina",
year = "2015",
abstract = "MOSFET electronic components are already the subject of several decades of research in various fields of dosimetry and radiation protection. Special interest appeared when these components are started to be used as dosimeters in radiotherapy with electron beams. However, if one looks much more serious in the wider scientific research horizon, all the results obtained in experiments with precisely defined energies of incident electrons can be used in other disciplines which consider the impacts spectra of cosmic radiation on electronic devices, which is especially importance for cosmic science and space research instrumentation. In this paper, one of the objectives was to examine the electrical characteristics specially designed ESAPMOS RADFET dosimeters in the experiments that were conducted on a linear accelerator installations. RADFET components are bombarded electron beams energy of 6 MeV and 8 MeV, and then are followed by changes in threshold voltage shift mean values depending on the change of absorbed dose is referred to as D(cGy) was determined in water. Conclusions performance RADFET components are more than encouraging in terms of further research to improve the linearity of the energy dependence as widely energy electrons. In the second part of the test complex structure of packaging components RADFET focus is placed on the determination of the energy deposited in layers that are of interest for the analysis of microscopic processes related to the recombination of radiation-induced electron-hole pairs. Transport incident electrons through all the layers of structure RADFET component type ESAPMOS was carried out numerical simulations of the Monte Carlo method using the software package FOTELP-2K12. On this occasion, were taken into account all the physical processes of interaction of electrons with materials given structure. When he conquered the numerical application of mathematical and physical model for determining the value of the absorbed energy as the energy deposited per unit mass in a given layers with different materials, it could be accessed defining physical shielding factor (PSF) for a given structure RADFET components. Physical shielding factor (PSF) is defined as the ratio of absorbed dose values, which in fact means that it is equal to the energy deposited when the RADFET is shielded with protection, and the RADFET without lid. When we know the energy dependence factor for PSF of RADFET with and without armour, can be carried out and the analysis of whether and to what extent the energy required compensating the electronic components. Monte Carlo simulations were performed for the transport of incident electrons from 4 MeV, 6 MeV, 8 MeV and 12 MeV. It can be concluded that the different energy of incident electrons there is a significant influence of material Kovar on the absorbed energy in SiO2 and Si layers structure RADFET, in cases where Kovar used among other things as physical protection.",
publisher = "Niš : RAD Association",
journal = "RAD 2015 : International Conference on Radiation and Applications in Various Fields of Research : Book of abstracts",
title = "Experiments with RADFET dosimeter in electron-beams irradiation and numerical computation of the physical shielding factor",
pages = "153-153",
url = "https://hdl.handle.net/21.15107/rcub_vinar_12151"
}

Stanković, S., Jakšić, A., Ilić, R., Nikolić, D., Lončar, B., Lazarević, Đ.,& Karadžić, K.. (2015). Experiments with RADFET dosimeter in electron-beams irradiation and numerical computation of the physical shielding factor. in RAD 2015 : International Conference on Radiation and Applications in Various Fields of Research : Book of abstracts
Niš : RAD Association., 153-153.
https://hdl.handle.net/21.15107/rcub_vinar_12151

Stanković S, Jakšić A, Ilić R, Nikolić D, Lončar B, Lazarević Đ, Karadžić K. Experiments with RADFET dosimeter in electron-beams irradiation and numerical computation of the physical shielding factor. in RAD 2015 : International Conference on Radiation and Applications in Various Fields of Research : Book of abstracts. 2015;:153-153.
https://hdl.handle.net/21.15107/rcub_vinar_12151 .

Stanković, Srboljub, Jakšić, Aleksandar, Ilić, Radovan, Nikolić, Dragana, Lončar, Boris, Lazarević, Đorđe, Karadžić, Katarina, "Experiments with RADFET dosimeter in electron-beams irradiation and numerical computation of the physical shielding factor" in RAD 2015 : International Conference on Radiation and Applications in Various Fields of Research : Book of abstracts (2015):153-153,
https://hdl.handle.net/21.15107/rcub_vinar_12151 .

TY  - CONF
AU  - Stanković, Srboljub
AU  - Ilić, Radovan
AU  - Živanović, Miloš
AU  - Osmokrović, Predrag
AU  - Lončar, Boris
PY  - 2013
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12344
AB  - U ovom radu je demonstrirana analiza dizajniranja RADFET dozimetra koja je bazirana na primeni numeričke metode Monte Karlo pri proceni uticaja titanijumskih legura kao izabranog materijala za poklopac pakovanja dozimetara. Sprovedene su Monte Karlo simulacije transporta fotona X i gama zračenja različitih energija kroz razmatranu strukturu RADFET dozimetra i pritom je proračunat energetski zavisan faktor zaštite (SEDF) koji je moguće definisati za elektronske komponente datog tipa. Uzimajući u obzir vrednosti SEDF za različite vrednosti incidentnih energija fotona i dobijene odgovarajuće deponovane energije u materijalnim zonama RADFET dozimetra, ustanovljeno je da je titanijumska legura sa cirkonijumom Ti-13Nb-13Zr pogodniji material za izradu poklopca za pakovanje.
PB  - Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore
C3  - 27. simpozijum DZZSCG : zbornik radova
T1  - Procena uticaja poklopca pakovanja od izabranih titanijumskih legura na energetsku zavisnost RADFET dozimetara u poljima gama i X zračenja
SP  - 443
EP  - 447
UR  - https://hdl.handle.net/21.15107/rcub_vinar_12344
ER  - 

@conference{
author = "Stanković, Srboljub and Ilić, Radovan and Živanović, Miloš and Osmokrović, Predrag and Lončar, Boris",
year = "2013",
abstract = "U ovom radu je demonstrirana analiza dizajniranja RADFET dozimetra koja je bazirana na primeni numeričke metode Monte Karlo pri proceni uticaja titanijumskih legura kao izabranog materijala za poklopac pakovanja dozimetara. Sprovedene su Monte Karlo simulacije transporta fotona X i gama zračenja različitih energija kroz razmatranu strukturu RADFET dozimetra i pritom je proračunat energetski zavisan faktor zaštite (SEDF) koji je moguće definisati za elektronske komponente datog tipa. Uzimajući u obzir vrednosti SEDF za različite vrednosti incidentnih energija fotona i dobijene odgovarajuće deponovane energije u materijalnim zonama RADFET dozimetra, ustanovljeno je da je titanijumska legura sa cirkonijumom Ti-13Nb-13Zr pogodniji material za izradu poklopca za pakovanje.",
publisher = "Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore",
journal = "27. simpozijum DZZSCG : zbornik radova",
title = "Procena uticaja poklopca pakovanja od izabranih titanijumskih legura na energetsku zavisnost RADFET dozimetara u poljima gama i X zračenja",
pages = "443-447",
url = "https://hdl.handle.net/21.15107/rcub_vinar_12344"
}

Stanković, S., Ilić, R., Živanović, M., Osmokrović, P.,& Lončar, B.. (2013). Procena uticaja poklopca pakovanja od izabranih titanijumskih legura na energetsku zavisnost RADFET dozimetara u poljima gama i X zračenja. in 27. simpozijum DZZSCG : zbornik radova
Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore., 443-447.
https://hdl.handle.net/21.15107/rcub_vinar_12344

Stanković S, Ilić R, Živanović M, Osmokrović P, Lončar B. Procena uticaja poklopca pakovanja od izabranih titanijumskih legura na energetsku zavisnost RADFET dozimetara u poljima gama i X zračenja. in 27. simpozijum DZZSCG : zbornik radova. 2013;:443-447.
https://hdl.handle.net/21.15107/rcub_vinar_12344 .

Stanković, Srboljub, Ilić, Radovan, Živanović, Miloš, Osmokrović, Predrag, Lončar, Boris, "Procena uticaja poklopca pakovanja od izabranih titanijumskih legura na energetsku zavisnost RADFET dozimetara u poljima gama i X zračenja" in 27. simpozijum DZZSCG : zbornik radova (2013):443-447,
https://hdl.handle.net/21.15107/rcub_vinar_12344 .

TY  - CONF
AU  - Stanković, Srboljub
AU  - Ilić, Radovan
AU  - Živanović, Miloš
AU  - Lončar, Boris
AU  - Davidović, Miloš
AU  - Milenković, Aleksandra
PY  - 2011
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12266
AB  - Legure titanijuma su vremenom pronašle brojne primenei u tehnologijama koje su vezane kako za industriju, tako i za programe istraživanja u radijacionom okruženju. Kako je izmedju ostalog, X-zračenje važan deo i kosmičkog zračenja, u ovom radu su sprovedene numeričke simulacije transporta fotona kroz različite materijale od titanijumskih legura u cilju razmatranja veze izmedju broja radijacionih defekata i apsorbovane energije gama zračenja. Korišćen je softver FOTELP-2K10 za Monte Karlo simulacije transporta fotona za odreñivanje apsorbovane energije zračenja u titanijumskim uzorcima. Numerički rezultati pokazuju izraženu zavisnost apsorpcije zračenja od različitih kombinacija komponenata u leguri. Rezultati dobijeni na ovaj način su značajni kada je u pitanju optimizacija strukture legura u cilju poboljšanja njihovih svojstava koja se odnose na zaštitu od jonizujućeg zračenja.
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 radiationabsorption characteristics of titanium alloys were studied in this paper. The photon transport Monte Carlosoftware was used for determining the energy deposited in titanium samples. The numerical results show thepronounced dependence of radiation absorption properties of different combinations of components in alloy. Theresults obtained are encouraging in respect of optimization of structure of alloys regarding their required features in radiation shielding.
PB  - Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore
C3  - 26. simpozijum DZZSCG : zbornik radova
T1  - Radijacioni defekti usled apsorpcije gama zračenja u titanijumskim legurama
T1  - Radiation absorption characteristics of titanium alloys
SP  - 33
EP  - 37
UR  - https://hdl.handle.net/21.15107/rcub_vinar_12266
ER  - 

@conference{
author = "Stanković, Srboljub and Ilić, Radovan and Živanović, Miloš and Lončar, Boris and Davidović, Miloš and Milenković, Aleksandra",
year = "2011",
abstract = "Legure titanijuma su vremenom pronašle brojne primenei u tehnologijama koje su vezane kako za industriju, tako i za programe istraživanja u radijacionom okruženju. Kako je izmedju ostalog, X-zračenje važan deo i kosmičkog zračenja, u ovom radu su sprovedene numeričke simulacije transporta fotona kroz različite materijale od titanijumskih legura u cilju razmatranja veze izmedju broja radijacionih defekata i apsorbovane energije gama zračenja. Korišćen je softver FOTELP-2K10 za Monte Karlo simulacije transporta fotona za odreñivanje apsorbovane energije zračenja u titanijumskim uzorcima. Numerički rezultati pokazuju izraženu zavisnost apsorpcije zračenja od različitih kombinacija komponenata u leguri. Rezultati dobijeni na ovaj način su značajni kada je u pitanju optimizacija strukture legura u cilju poboljšanja njihovih svojstava koja se odnose na zaštitu od jonizujućeg zračenja., 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 radiationabsorption characteristics of titanium alloys were studied in this paper. The photon transport Monte Carlosoftware was used for determining the energy deposited in titanium samples. The numerical results show thepronounced dependence of radiation absorption properties of different combinations of components in alloy. Theresults obtained are encouraging in respect of optimization of structure of alloys regarding their required features in radiation shielding.",
publisher = "Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore",
journal = "26. simpozijum DZZSCG : zbornik radova",
title = "Radijacioni defekti usled apsorpcije gama zračenja u titanijumskim legurama, Radiation absorption characteristics of titanium alloys",
pages = "33-37",
url = "https://hdl.handle.net/21.15107/rcub_vinar_12266"
}

Stanković, S., Ilić, R., Živanović, M., Lončar, B., Davidović, M.,& Milenković, A.. (2011). Radijacioni defekti usled apsorpcije gama zračenja u titanijumskim legurama. in 26. simpozijum DZZSCG : zbornik radova
Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore., 33-37.
https://hdl.handle.net/21.15107/rcub_vinar_12266

Stanković S, Ilić R, Živanović M, Lončar B, Davidović M, Milenković A. Radijacioni defekti usled apsorpcije gama zračenja u titanijumskim legurama. in 26. simpozijum DZZSCG : zbornik radova. 2011;:33-37.
https://hdl.handle.net/21.15107/rcub_vinar_12266 .

Stanković, Srboljub, Ilić, Radovan, Živanović, Miloš, Lončar, Boris, Davidović, Miloš, Milenković, Aleksandra, "Radijacioni defekti usled apsorpcije gama zračenja u titanijumskim legurama" in 26. simpozijum DZZSCG : zbornik radova (2011):33-37,
https://hdl.handle.net/21.15107/rcub_vinar_12266 .

TY  - CONF
AU  - Stanković, Srboljub
AU  - Ilić, Radovan
AU  - Kovačević, Milojko
AU  - Vukčević, Mladen
AU  - Davidović, Dragomir
AU  - Lazarević, Đorđe
AU  - Davidović, Miloš
PY  - 2009
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12265
AB  - U praksi projektovanja zaštite od zračenja na nuklearnim instalacijama (akceleratori, nuklearni reaktori, instalacije za protonsku terapiju u medicini, itd.) od interesa je proračun prinosa sekundarnih neutrona u odnosu na njihov energetski spektar i ugaonu distribuciju. Pored eksperimentalnog pristupa kada je u pitanju pre svega provera kvaliteta projektovane zaštite, tome prethodi izbor i primena odgovarajuće metode proračuna zaštite za definisani incidentni snop čestica i materijal mete. U ovom radu razmatra se ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV sa debelom metom od bakra.
PB  - Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore
C3  - 25. simpozijum DZZSCG : zbornik radova
T1  - Ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV Sa debelom metom od bakra
SP  - 151
EP  - 155
UR  - https://hdl.handle.net/21.15107/rcub_vinar_12265
ER  - 

@conference{
author = "Stanković, Srboljub and Ilić, Radovan and Kovačević, Milojko and Vukčević, Mladen and Davidović, Dragomir and Lazarević, Đorđe and Davidović, Miloš",
year = "2009",
abstract = "U praksi projektovanja zaštite od zračenja na nuklearnim instalacijama (akceleratori, nuklearni reaktori, instalacije za protonsku terapiju u medicini, itd.) od interesa je proračun prinosa sekundarnih neutrona u odnosu na njihov energetski spektar i ugaonu distribuciju. Pored eksperimentalnog pristupa kada je u pitanju pre svega provera kvaliteta projektovane zaštite, tome prethodi izbor i primena odgovarajuće metode proračuna zaštite za definisani incidentni snop čestica i materijal mete. U ovom radu razmatra se ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV sa debelom metom od bakra.",
publisher = "Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore",
journal = "25. simpozijum DZZSCG : zbornik radova",
title = "Ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV Sa debelom metom od bakra",
pages = "151-155",
url = "https://hdl.handle.net/21.15107/rcub_vinar_12265"
}

Stanković, S., Ilić, R., Kovačević, M., Vukčević, M., Davidović, D., Lazarević, Đ.,& Davidović, M.. (2009). Ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV Sa debelom metom od bakra. in 25. simpozijum DZZSCG : zbornik radova
Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore., 151-155.
https://hdl.handle.net/21.15107/rcub_vinar_12265

Stanković S, Ilić R, Kovačević M, Vukčević M, Davidović D, Lazarević Đ, Davidović M. Ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV Sa debelom metom od bakra. in 25. simpozijum DZZSCG : zbornik radova. 2009;:151-155.
https://hdl.handle.net/21.15107/rcub_vinar_12265 .

Stanković, Srboljub, Ilić, Radovan, Kovačević, Milojko, Vukčević, Mladen, Davidović, Dragomir, Lazarević, Đorđe, Davidović, Miloš, "Ugaona distribucija spektralne gustine neutrona prilikom interakcije snopa protona energije 50 MeV Sa debelom metom od bakra" in 25. simpozijum DZZSCG : zbornik radova (2009):151-155,
https://hdl.handle.net/21.15107/rcub_vinar_12265 .

TY  - CONF
AU  - Ilić, Radovan
AU  - Marinković, Predrag
AU  - Stanković, Srboljub
AU  - Kaljević, Jelica
PY  - 2007
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/12261
AB  - U simulaciji prolaza čestica tehnikama Monte Karlo aktuelni geometrijski moduli upotrebljavaju površine prvog i drugog reda (FOTELP, PENELOPE, SHIELD, GEANT), a nekad i četvrtog reda(MCNP5), da opišu složene geometrijske forme.. Sve veća primena tehnika Monte Karlo u medicini oslanja se na vokselizovane geometrijske forme koje se dobijaju vokselizaciom fantoma ili iz CT podataka. Ogroman broj tela (voxela) u tom slučaju otežava primenu konstruktivne geometrije. Eefikasniji pristup tom problemu zasniva se na primeni virtuelnog voksela.Ovde se saopštavaju rezultati upotrebe virtuelnog voksela na anatomiju tela i organa upotrebom CT podataka.
AB  - Geometry modules in particle transport simulation codes with Monte Carlo techniques use surfaces of first and second order, sometimes even a fourth order surfaces, to be able to describe complex geometrical shapes. Constructive quadric geometry dominates in all leading software packages. Increasing application of Monte Carlo techniques in medicine is associated with voxelized geometry forms. Huge number of bodies present in this case makes the use of constructive geometry more difficult. The paper describes an efficient approach to this problem by virtual voxel application, where optical distance to the boundary is obtained, and 3D voxel indices give information about the materials present in voxel.
PB  - Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore
C3  - 24. simpozijum DZZSCG : zbornik radova
T1  - Primena virtuelng voksela pri upotrebi CT podataka u modelovanju trajektorije čestice tehnikama Monte Karlo
T1  - Usage of virtual voxel with CT data in particles trajectory modeling by Monte Carlo techniques
SP  - 233
EP  - 237
UR  - https://hdl.handle.net/21.15107/rcub_vinar_12261
ER  - 

@conference{
author = "Ilić, Radovan and Marinković, Predrag and Stanković, Srboljub and Kaljević, Jelica",
year = "2007",
abstract = "U simulaciji prolaza čestica tehnikama Monte Karlo aktuelni geometrijski moduli upotrebljavaju površine prvog i drugog reda (FOTELP, PENELOPE, SHIELD, GEANT), a nekad i četvrtog reda(MCNP5), da opišu složene geometrijske forme.. Sve veća primena tehnika Monte Karlo u medicini oslanja se na vokselizovane geometrijske forme koje se dobijaju vokselizaciom fantoma ili iz CT podataka. Ogroman broj tela (voxela) u tom slučaju otežava primenu konstruktivne geometrije. Eefikasniji pristup tom problemu zasniva se na primeni virtuelnog voksela.Ovde se saopštavaju rezultati upotrebe virtuelnog voksela na anatomiju tela i organa upotrebom CT podataka., Geometry modules in particle transport simulation codes with Monte Carlo techniques use surfaces of first and second order, sometimes even a fourth order surfaces, to be able to describe complex geometrical shapes. Constructive quadric geometry dominates in all leading software packages. Increasing application of Monte Carlo techniques in medicine is associated with voxelized geometry forms. Huge number of bodies present in this case makes the use of constructive geometry more difficult. The paper describes an efficient approach to this problem by virtual voxel application, where optical distance to the boundary is obtained, and 3D voxel indices give information about the materials present in voxel.",
publisher = "Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore",
journal = "24. simpozijum DZZSCG : zbornik radova",
title = "Primena virtuelng voksela pri upotrebi CT podataka u modelovanju trajektorije čestice tehnikama Monte Karlo, Usage of virtual voxel with CT data in particles trajectory modeling by Monte Carlo techniques",
pages = "233-237",
url = "https://hdl.handle.net/21.15107/rcub_vinar_12261"
}

Ilić, R., Marinković, P., Stanković, S.,& Kaljević, J.. (2007). Primena virtuelng voksela pri upotrebi CT podataka u modelovanju trajektorije čestice tehnikama Monte Karlo. in 24. simpozijum DZZSCG : zbornik radova
Beograd : Institut za nuklearne nauke "Vinča" : Društvo za zaštitu od zračenja Srbije i Crne Gore., 233-237.
https://hdl.handle.net/21.15107/rcub_vinar_12261

Ilić R, Marinković P, Stanković S, Kaljević J. Primena virtuelng voksela pri upotrebi CT podataka u modelovanju trajektorije čestice tehnikama Monte Karlo. in 24. simpozijum DZZSCG : zbornik radova. 2007;:233-237.
https://hdl.handle.net/21.15107/rcub_vinar_12261 .

Ilić, Radovan, Marinković, Predrag, Stanković, Srboljub, Kaljević, Jelica, "Primena virtuelng voksela pri upotrebi CT podataka u modelovanju trajektorije čestice tehnikama Monte Karlo" in 24. simpozijum DZZSCG : zbornik radova (2007):233-237,
https://hdl.handle.net/21.15107/rcub_vinar_12261 .