In the gamma-ray spectroscopy field, the radiometric examination for small quantities of natural samples is extremely significant. Therefore, the gamma-ray spectrometry calibration process must be prepared with good precision for several energies, matrices of sources or samples, and source-to-detector shapes. This manuscript considers a new uncomplicated analytical computation technique to calculate the effective geometrical solid angle and the efficiency of cubic scintillation crystal with a side cylindrical hole. The computations can be done by using a simple method, with a few essential limitations, that describes radioactive point sources located inside the side cylindrical hole and a high-efficiency cubic NaI(Tl) detector, come together with a low background as well. The technique stands on a trouble-free solid angle analytical formula for the detection system, using an accurate relation for the detector cavity, united with rough formulas controlling the interactions in the gamma-ray source and the materials introduced in between the source and the gamma-ray spectrometry. This new technique is not restricted to certain sources, because several source shapes can correspond to a homogeneous huge number of point sources and the detector geometry can be represented as a set of border points. The technique simply can be useful to obtain the full-energy peak efficiency in the future, challenging developments for low-energy gamma-ray spectroscopy.
{"title":"Analytical computation technique for calculation the effective geometrical solid angle and the efficiency of cubic scintillation crystal with side cylindrical hole","authors":"M. Badawi, A. Thabet","doi":"10.2298/ntrp2202091b","DOIUrl":"https://doi.org/10.2298/ntrp2202091b","url":null,"abstract":"In the gamma-ray spectroscopy field, the radiometric examination for small quantities of natural samples is extremely significant. Therefore, the gamma-ray spectrometry calibration process must be prepared with good precision for several energies, matrices of sources or samples, and source-to-detector shapes. This manuscript considers a new uncomplicated analytical computation technique to calculate the effective geometrical solid angle and the efficiency of cubic scintillation crystal with a side cylindrical hole. The computations can be done by using a simple method, with a few essential limitations, that describes radioactive point sources located inside the side cylindrical hole and a high-efficiency cubic NaI(Tl) detector, come together with a low background as well. The technique stands on a trouble-free solid angle analytical formula for the detection system, using an accurate relation for the detector cavity, united with rough formulas controlling the interactions in the gamma-ray source and the materials introduced in between the source and the gamma-ray spectrometry. This new technique is not restricted to certain sources, because several source shapes can correspond to a homogeneous huge number of point sources and the detector geometry can be represented as a set of border points. The technique simply can be useful to obtain the full-energy peak efficiency in the future, challenging developments for low-energy gamma-ray spectroscopy.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548260","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Radon exhalation rate is the rate of radioactive radon gas that escapes from the soil into the atmosphere. In this study exhalation rate of radon was measured for 33 samples of soil, in four districts of Duhok province, using two different techniques: one using radon concentration and other using radium content, by both alpha and gamma spectroscopy. For the radon measurement, alpha-sensitive RAD7 detector was used. While in the second method, radon exhalation rate was expressed as a function of radium concentration, measured by well type NaI (Tl) detector and other soil parameters. Analysis, shows that the average of radon exhalation rate, by the first technique, varies from 14.6 ? 3.2 to 55.7 ? 1.6 Bqm-2h-1, while by the second technique, it varies from 13.3 ? 2.4 to 50.6 ? 4.1 Bqm-2h-1. Overall, the measured values, for both methods at all the sample points, present a good correlation and less than global mean average recommendation.
{"title":"Soil radon exhalation rate measurement in Duhok city by two techniques","authors":"W. Alhamdi, M. Abdullah","doi":"10.2298/ntrp2203229a","DOIUrl":"https://doi.org/10.2298/ntrp2203229a","url":null,"abstract":"Radon exhalation rate is the rate of radioactive radon gas that escapes from the soil into the atmosphere. In this study exhalation rate of radon was measured for 33 samples of soil, in four districts of Duhok province, using two different techniques: one using radon concentration and other using radium content, by both alpha and gamma spectroscopy. For the radon measurement, alpha-sensitive RAD7 detector was used. While in the second method, radon exhalation rate was expressed as a function of radium concentration, measured by well type NaI (Tl) detector and other soil parameters. Analysis, shows that the average of radon exhalation rate, by the first technique, varies from 14.6 ? 3.2 to 55.7 ? 1.6 Bqm-2h-1, while by the second technique, it varies from 13.3 ? 2.4 to 50.6 ? 4.1 Bqm-2h-1. Overall, the measured values, for both methods at all the sample points, present a good correlation and less than global mean average recommendation.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549468","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Boron neutron capture therapy is a unique treatment method that aims to kill the tumor cells with the help of heavy particles. Particles resulting from the interaction of the tumor region containing 10B atoms with thermal or epithermal neutrons have the most important role in this treatment method. In this study, gamma radiation reaching healthy tissues, which is the result of 10B(n,a)7Li reaction, was investigated. A simulation suitable for boron neutron capture therapy treatment, including the human head model, was created by the Monte Carlo N-Particle (MCNP) program. By using five different neutron energies, the gamma radiations resulting from the 10B(n,a)7Li reaction in the determined regions, close to the tumor tissue, were investigated. It was observed that the healthy tissue between the tumor area and the surface is exposed to the highest gamma flux and the highest gamma radiation absorption. It was also observed that these values increase as neutron energy decreases. It was found that the gamma doses received by some regions outside the neutron irradiation area could be significant. It has been understood that the change in neutron energy may cause significant changes in gamma radiation values reaching healthy tissues, especially in regions close to the surface. In boron neutron capture therapy treatments, the neutrons sent to the tumor should be selected depending on the location of the tumor and the size of the tumor area. This study contains significant data about photon doses in healthy tissues around the brain region treated using different neutron energies with the boron neutron capture therapy technique.
{"title":"Investigation of photon doses reaching healthy tissues in the use of different neutron energies in boron neutron capture therapy","authors":"T. Tuğrul","doi":"10.2298/ntrp2204334t","DOIUrl":"https://doi.org/10.2298/ntrp2204334t","url":null,"abstract":"Boron neutron capture therapy is a unique treatment method that aims to kill the tumor cells with the help of heavy particles. Particles resulting from the interaction of the tumor region containing 10B atoms with thermal or epithermal neutrons have the most important role in this treatment method. In this study, gamma radiation reaching healthy tissues, which is the result of 10B(n,a)7Li reaction, was investigated. A simulation suitable for boron neutron capture therapy treatment, including the human head model, was created by the Monte Carlo N-Particle (MCNP) program. By using five different neutron energies, the gamma radiations resulting from the 10B(n,a)7Li reaction in the determined regions, close to the tumor tissue, were investigated. It was observed that the healthy tissue between the tumor area and the surface is exposed to the highest gamma flux and the highest gamma radiation absorption. It was also observed that these values increase as neutron energy decreases. It was found that the gamma doses received by some regions outside the neutron irradiation area could be significant. It has been understood that the change in neutron energy may cause significant changes in gamma radiation values reaching healthy tissues, especially in regions close to the surface. In boron neutron capture therapy treatments, the neutrons sent to the tumor should be selected depending on the location of the tumor and the size of the tumor area. This study contains significant data about photon doses in healthy tissues around the brain region treated using different neutron energies with the boron neutron capture therapy technique.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550511","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
N. Obajdin, Djeni Smilovic-Radojcic, David Rajlić, Manda Švabić-Kolacio, S. Jurković
Advances of radiation delivery devices have increased the complexity of the radiation oncology treatments. Herewith, outcome of the treatment, as well as patient safety, strongly depend on the consistency of absorbed dose delivery. Both can be ensured by comprehensive system of verification of calculated absorbed dose distributions. Standard method is evaluation of calculated absorbed dose distribution according to gamma method, using a 2-D detector and a homogeneous phantom, to obtain measured dose distribution. Purpose of this research was to investigate the influence of tolerance criteria on gamma passing rate. Additionally, the agreement in heterogeneous phantom was analysed. Absorbed dose calculations were performed using systems Monaco and XiO. Detector with 1020 ionization chambers in homogeneous phantom and semi-anthropomorphic phantom was used for measurements. Absorbed dose distributions of around 3500 patients were analysed using gamma method. In homogeneous phantom, average gamma passing rates were within tolerance for 3 %/2 mm. For measurements in heterogeneous media, the highest average gamma passing rate was obtained for small volumes of medium treatment complexity (??=93.84%), while large volumes of treatment with low complexity yielded the lowest gamma passing rates (??= 83.22%).
{"title":"Impact of stringent tolerance criteria on verification of absorbed dose distributions and evaluation through inhomogeneous media","authors":"N. Obajdin, Djeni Smilovic-Radojcic, David Rajlić, Manda Švabić-Kolacio, S. Jurković","doi":"10.2298/ntrp2202138o","DOIUrl":"https://doi.org/10.2298/ntrp2202138o","url":null,"abstract":"Advances of radiation delivery devices have increased the complexity of the radiation oncology treatments. Herewith, outcome of the treatment, as well as patient safety, strongly depend on the consistency of absorbed dose delivery. Both can be ensured by comprehensive system of verification of calculated absorbed dose distributions. Standard method is evaluation of calculated absorbed dose distribution according to gamma method, using a 2-D detector and a homogeneous phantom, to obtain measured dose distribution. Purpose of this research was to investigate the influence of tolerance criteria on gamma passing rate. Additionally, the agreement in heterogeneous phantom was analysed. Absorbed dose calculations were performed using systems Monaco and XiO. Detector with 1020 ionization chambers in homogeneous phantom and semi-anthropomorphic phantom was used for measurements. Absorbed dose distributions of around 3500 patients were analysed using gamma method. In homogeneous phantom, average gamma passing rates were within tolerance for 3 %/2 mm. For measurements in heterogeneous media, the highest average gamma passing rate was obtained for small volumes of medium treatment complexity (??=93.84%), while large volumes of treatment with low complexity yielded the lowest gamma passing rates (??= 83.22%).","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548825","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
To assess the characteristics of 13N decay, a monitoring method of the primary loop leakage rate based on the ?-? coincidence method was proposed. In this work, sampling and measurement devices were designed, in which NaI (Tl) crystals were used as coincidence detectors. The Geant4 simulation method was used to study the relationship between the efficiency e and capacity V change of different devices, and the eV value under the corresponding capacity was obtained. According to the value of eV, the optimal sampling and measurement device was determined, and then the detection efficiency of the device was calibrated experimentally. Taking the 600 000 kW reactor of Qinshan Phase II as the research object, the lower limit of detection was discussed. When the sampling point was located in the fume hood of the control rod drive mechanism, the theoretical lower limit of the coincidence method was 0.756 Lh-1.
{"title":"Research on leak monitoring of the primary circuit of a pressurized water reactor based on the 13N coincidence method","authors":"Yue Zhao, G. Qu, Jian Zhou","doi":"10.2298/ntrp2204308z","DOIUrl":"https://doi.org/10.2298/ntrp2204308z","url":null,"abstract":"To assess the characteristics of 13N decay, a monitoring method of the primary loop leakage rate based on the ?-? coincidence method was proposed. In this work, sampling and measurement devices were designed, in which NaI (Tl) crystals were used as coincidence detectors. The Geant4 simulation method was used to study the relationship between the efficiency e and capacity V change of different devices, and the eV value under the corresponding capacity was obtained. According to the value of eV, the optimal sampling and measurement device was determined, and then the detection efficiency of the device was calibrated experimentally. Taking the 600 000 kW reactor of Qinshan Phase II as the research object, the lower limit of detection was discussed. When the sampling point was located in the fume hood of the control rod drive mechanism, the theoretical lower limit of the coincidence method was 0.756 Lh-1.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550859","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Uranium dioxied is used as a nuclear fuel. Depending on the temperature and oxygen partial pressure, it is incredibly versatile and can accept a wide variety of stoichiometry. Many methods are used to estimate the non-stoichiometric O/U ratio such as the coulometric titration, gravimetric and voltammetric methods. These methods have some disadvantages and may be time and cost-consuming. This work develops an approach to determine the stoichiometric ratio by using MCNP-5 code and hyper pure germanium detector to estimate the count rate at 185.7 keV for UO2 pellets. The studied pellets are proposed to have 235U mass content (3 %, 4 %, and 5 %) and 1 cm away from the detector. The mass of the oxide within the pellets is 7.8995 grams. The relation between volume and density has been studied during different steps in which temperature increases. Finally, a reliable model is established to describe the process of converting green pellets to sintered pellets. The model is supported by employing artificial intelligence to predict some features and the overall correlation equals 0.99929.
{"title":"Developing a reliable approach to estimate the stoichiometric ratio of O/U in UO2 pellets using MCNP-5 and artificial intelligence","authors":"S. Shaban, Ahmad Agha, Karim Aladham","doi":"10.2298/ntrp2204302s","DOIUrl":"https://doi.org/10.2298/ntrp2204302s","url":null,"abstract":"Uranium dioxied is used as a nuclear fuel. Depending on the temperature and oxygen partial pressure, it is incredibly versatile and can accept a wide variety of stoichiometry. Many methods are used to estimate the non-stoichiometric O/U ratio such as the coulometric titration, gravimetric and voltammetric methods. These methods have some disadvantages and may be time and cost-consuming. This work develops an approach to determine the stoichiometric ratio by using MCNP-5 code and hyper pure germanium detector to estimate the count rate at 185.7 keV for UO2 pellets. The studied pellets are proposed to have 235U mass content (3 %, 4 %, and 5 %) and 1 cm away from the detector. The mass of the oxide within the pellets is 7.8995 grams. The relation between volume and density has been studied during different steps in which temperature increases. Finally, a reliable model is established to describe the process of converting green pellets to sintered pellets. The model is supported by employing artificial intelligence to predict some features and the overall correlation equals 0.99929.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550834","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Betatrons have the advantages of small size, lightweight, and simple operation. They are widely used in non-destructive testing, cargo, and vehicle safety inspection systems. Magnetic field distribution is an essential parameter of betatrons and has been investigated via experimental methods. Recently, simulations have been performed for the magnetic field distribution generated by different magnetic pole parameters. In this study, the finite element method is employed to simulate the magnetic field distribution. The effects of the different magnetic end face opening angles, pole protrusion sizes, number of central magnetic pads, and magnetic pole bottom width on the magnetic field distribution are simulated. Based on the simulation results, magnetic poles are developed, and the magnetic field distribution is measured by a gauss meter. The relative error of the measured and simulated equilibrium orbit is 2.1 %, and the relative error of the magnetic field decay index is 3.3 %. The magnetic field distribution can satisfy the essential conditions that the magnetic field at equilibrium orbit of the betatron is equal to half of the average magnetic field within equilibrium orbit and the magnetic field decay index is greater than 0 and less than 1. The results show that the finite element simulation method and established model have high reliability and effectively improve the design accuracy of magnetic poles.
{"title":"Simulation analysis and experiment of magnetic pole shape influence on betatron magnetic field","authors":"Qi Liu, Ren-Bo Wang, Jin-Hai Li, Haitao Wang, Hailei Chen, Bin Tang","doi":"10.2298/ntrp2201001l","DOIUrl":"https://doi.org/10.2298/ntrp2201001l","url":null,"abstract":"Betatrons have the advantages of small size, lightweight, and simple operation. They are widely used in non-destructive testing, cargo, and vehicle safety inspection systems. Magnetic field distribution is an essential parameter of betatrons and has been investigated via experimental methods. Recently, simulations have been performed for the magnetic field distribution generated by different magnetic pole parameters. In this study, the finite element method is employed to simulate the magnetic field distribution. The effects of the different magnetic end face opening angles, pole protrusion sizes, number of central magnetic pads, and magnetic pole bottom width on the magnetic field distribution are simulated. Based on the simulation results, magnetic poles are developed, and the magnetic field distribution is measured by a gauss meter. The relative error of the measured and simulated equilibrium orbit is 2.1 %, and the relative error of the magnetic field decay index is 3.3 %. The magnetic field distribution can satisfy the essential conditions that the magnetic field at equilibrium orbit of the betatron is equal to half of the average magnetic field within equilibrium orbit and the magnetic field decay index is greater than 0 and less than 1. The results show that the finite element simulation method and established model have high reliability and effectively improve the design accuracy of magnetic poles.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68547875","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Z. Zuhair, W. Luthfi, S. Sriyono, S. Suwoto, T. Setiadipura
The inherent safety feature of a pebble-bed reactor can be observed from its kinetic parameters. Proper modeling for calculating the reactor kinetic is also a concern for safe operation during normal and transient conditions. This study is intended to investigate the kinetic parameters characteristics of a pebble bed reactor using HTR-Proteus. A series of calculations were conducted using MCNP6 code and ENDF/B-VII library. The calculation results show that the negative value on core temperature reactivity is affected dominantly by the Doppler broadening effect. Prompt neutron lifetime l and mean generation time ? are slightly changed due to an increase in fuel temperature, moderator, and reflector that changed the neutron moderation and absorption over this part of the reactor. For (Th, U)O2, UO2, and PuO2 cores, the effective delayed neutron fraction ?eff values are more influenced by 233U, 235U, and 239Pu, respectively. In terms of stability during reactivity insertion, the UO 2 core is more stable and easier to control because its ?eff value is the largest compared to (Th,U)O2 and PuO 2 cores. It can be concluded that temperature must be controlled because it does not only affect the reactivity but also kinetic parameters as part of developing inherent safety features on the pebble-bed reactor.
{"title":"Study on kinetic parameters characteristics of pebble bed reactor using HTR-proteus facility","authors":"Z. Zuhair, W. Luthfi, S. Sriyono, S. Suwoto, T. Setiadipura","doi":"10.2298/ntrp2202119z","DOIUrl":"https://doi.org/10.2298/ntrp2202119z","url":null,"abstract":"The inherent safety feature of a pebble-bed reactor can be observed from its kinetic parameters. Proper modeling for calculating the reactor kinetic is also a concern for safe operation during normal and transient conditions. This study is intended to investigate the kinetic parameters characteristics of a pebble bed reactor using HTR-Proteus. A series of calculations were conducted using MCNP6 code and ENDF/B-VII library. The calculation results show that the negative value on core temperature reactivity is affected dominantly by the Doppler broadening effect. Prompt neutron lifetime l and mean generation time ? are slightly changed due to an increase in fuel temperature, moderator, and reflector that changed the neutron moderation and absorption over this part of the reactor. For (Th, U)O2, UO2, and PuO2 cores, the effective delayed neutron fraction ?eff values are more influenced by 233U, 235U, and 239Pu, respectively. In terms of stability during reactivity insertion, the UO 2 core is more stable and easier to control because its ?eff value is the largest compared to (Th,U)O2 and PuO 2 cores. It can be concluded that temperature must be controlled because it does not only affect the reactivity but also kinetic parameters as part of developing inherent safety features on the pebble-bed reactor.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548108","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Milena Živković, T. Miladinović, A. Miladinović, Una Molnar, D. Krstić
This paper illustrates the potential of the FOTELP-VOX code, a modification of the general-purpose FOTELP code, combining Monte Carlo techniques to simulate particle transportation from an external source through the internal organs, resulting in a 3-D absorbed dose distribution. The study shows the comparison of results obtained by FOTELP software and the volumetric modulated arc therapy technique. This planning technique with two full arcs was applied, and the plan was created to destroy the diseased tissue in the eye tumor bed and avoid damage to surrounding healthy tissue, for one patient. The dose coverage, homogeneity index, conformity index of the target, and the dose volumes of critical structures were calculated. Good agreement of the results for absorbed dose in the human eye was obtained using these two techniques.
{"title":"Absorbed dose distribution in human eye simulated by FOTELP-VOX code and verified by volumetric modulated arc therapy treatment plan","authors":"Milena Živković, T. Miladinović, A. Miladinović, Una Molnar, D. Krstić","doi":"10.2298/ntrp2201078z","DOIUrl":"https://doi.org/10.2298/ntrp2201078z","url":null,"abstract":"This paper illustrates the potential of the FOTELP-VOX code, a modification of the general-purpose FOTELP code, combining Monte Carlo techniques to simulate particle transportation from an external source through the internal organs, resulting in a 3-D absorbed dose distribution. The study shows the comparison of results obtained by FOTELP software and the volumetric modulated arc therapy technique. This planning technique with two full arcs was applied, and the plan was created to destroy the diseased tissue in the eye tumor bed and avoid damage to surrounding healthy tissue, for one patient. The dose coverage, homogeneity index, conformity index of the target, and the dose volumes of critical structures were calculated. Good agreement of the results for absorbed dose in the human eye was obtained using these two techniques.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548148","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nemanja Arandjelovic, Dušan P. Nikezić, Uzahir R. Ramadani, I. Lazović, Nikola Mirkov, P. Osmokrović
The research presents an experiment with a model of an electronic generator for energy injection into the plasma of a fusion reactor. By recording a non-ionizing field in the vicinity of a fusion reactor, it was determined that this field has an extremely high growth rate. At the site of the maximum intensity of the field of non-ionizing radiation, commercial surge arresters with a flexible model of surge arresters were used for experimentation. It has been found that the commercial surge arresters have an efficiency of about 20%. For the efficiency of the flexible model, it was found to be slightly less than 40% (and to be achieved by the application of alpha particle radiation). Since neither of these efficiencies guarantee reliable operation of the gas-filled surge arrester, it was concluded that essential electronics in the vicinity of the fusion generator must be protected. However, since this protection can only be implemented in a fusion reactor, the fact remains that the environment of such a reactor is extremely contaminated with non-ionizing radiation. Commercial surge voltages are isolated for testing since the protection of electronic circuits from fast overvoltages is a critical point for the functioning of modern electronics.
{"title":"The efficiency of gas-filled surge arresters in the environment contaminated by non-ionizing radiation of fusion reactors","authors":"Nemanja Arandjelovic, Dušan P. Nikezić, Uzahir R. Ramadani, I. Lazović, Nikola Mirkov, P. Osmokrović","doi":"10.2298/ntrp2201051a","DOIUrl":"https://doi.org/10.2298/ntrp2201051a","url":null,"abstract":"The research presents an experiment with a model of an electronic generator for energy injection into the plasma of a fusion reactor. By recording a non-ionizing field in the vicinity of a fusion reactor, it was determined that this field has an extremely high growth rate. At the site of the maximum intensity of the field of non-ionizing radiation, commercial surge arresters with a flexible model of surge arresters were used for experimentation. It has been found that the commercial surge arresters have an efficiency of about 20%. For the efficiency of the flexible model, it was found to be slightly less than 40% (and to be achieved by the application of alpha particle radiation). Since neither of these efficiencies guarantee reliable operation of the gas-filled surge arrester, it was concluded that essential electronics in the vicinity of the fusion generator must be protected. However, since this protection can only be implemented in a fusion reactor, the fact remains that the environment of such a reactor is extremely contaminated with non-ionizing radiation. Commercial surge voltages are isolated for testing since the protection of electronic circuits from fast overvoltages is a critical point for the functioning of modern electronics.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548229","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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