In fluoroscopy guided interventional procedures, ceiling suspended screen is used to protect personel for scattered X-ray radiation arising from patents. The correct positioning of the screen is crucial for proper occupational radiation protection. The proposed solution in this paper provides reliable and efficient protection from scattered radiation, based on X-ray device and the protective screen merging into one system via an appropriate interface. After the initial manual positioning, automatic repositioning of the screen is ?xecuted, by curving the screen laterally, clockwise or counterclockwise, and then with the upper or lower edge forward. All potential clinical situations were analyzed, considering need for screen position correction: the semi-automatic solution is designed and realized to follow the medical procedure in order to keep the efficient level of staff radiation protection. Furthermore, the assessment of the occupational radiation dose, provided for screen position optimization, will be imported in the radiation dose structural report. With application of the universal interface, the presented solution can be applied not only on newly manufactured ones, but on existing C-arm X-ray devices as well.
{"title":"Semi - automatic positioning of the protective screen based on integration with C-arm X-ray device","authors":"M. Antić","doi":"10.2298/ntrp201210002a","DOIUrl":"https://doi.org/10.2298/ntrp201210002a","url":null,"abstract":"In fluoroscopy guided interventional procedures, ceiling suspended screen is used to protect personel for scattered X-ray radiation arising from patents. The correct positioning of the screen is crucial for proper occupational radiation protection. The proposed solution in this paper provides reliable and efficient protection from scattered radiation, based on X-ray device and the protective screen merging into one system via an appropriate interface. After the initial manual positioning, automatic repositioning of the screen is ?xecuted, by curving the screen laterally, clockwise or counterclockwise, and then with the upper or lower edge forward. All potential clinical situations were analyzed, considering need for screen position correction: the semi-automatic solution is designed and realized to follow the medical procedure in order to keep the efficient level of staff radiation protection. Furthermore, the assessment of the occupational radiation dose, provided for screen position optimization, will be imported in the radiation dose structural report. With application of the universal interface, the presented solution can be applied not only on newly manufactured ones, but on existing C-arm X-ray devices as well.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68545662","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}
Amro Obeid, B. El, Samad El, Z. Alsayed, R. Awad, M. Badawi
The X-rays of the narrow-spectrum N-series ranging from 40 kV to 150 kV were used to determine the radiation attenuation ability of a new category of a polymer composite fabricated for shielding purposes. High density polyethylene was synthesized through a compression molding technique, and incorporated with various filler amounts (10, 15, 25, and 35 wt.%) of bulk micro-sized WO 3 (Sample A), two WO 3 nanoparticles 45 nm (Sample B), and 24 nm (Sample C). The WO 3 filler was identified and characterized using X-ray diffraction and a transmission electron microscope. The mass distribution of the chemical elements of the synthesized composites was determined by energy dispersive X-ray analysis. The obtained results of the different attenuation parameters revealed that the particle size and weight fraction of WO particles have an outstanding effect on the X-ray shielding ability of this composite. The 3 experimental measurements of the mass attenuation coefficients were compared to the theoretical values tabulated in the NIST databases XCOM and FFAST. The mass attenuation coefficient was increased with the increment of WO 3 wt.% as well as with the decrease of the WO 3 particle size. This improvement in the attenuation parameters of the NP(C) composite suggests their promising applications in radiation protection at the diagnostic level.
{"title":"Effects of different nano size and bulk WO3 enriched by HDPE composites on attenuation of the X-ray narrow spectrum","authors":"Amro Obeid, B. El, Samad El, Z. Alsayed, R. Awad, M. Badawi","doi":"10.2298/ntrp2104315o","DOIUrl":"https://doi.org/10.2298/ntrp2104315o","url":null,"abstract":"The X-rays of the narrow-spectrum N-series ranging from 40 kV to 150 kV were used to determine the radiation attenuation ability of a new category of a polymer composite fabricated for shielding purposes. High density polyethylene was synthesized through a compression molding technique, and incorporated with various filler amounts (10, 15, 25, and 35 wt.%) of bulk micro-sized WO 3 (Sample A), two WO 3 nanoparticles 45 nm (Sample B), and 24 nm (Sample C). The WO 3 filler was identified and characterized using X-ray diffraction and a transmission electron microscope. The mass distribution of the chemical elements of the synthesized composites was determined by energy dispersive X-ray analysis. The obtained results of the different attenuation parameters revealed that the particle size and weight fraction of WO particles have an outstanding effect on the X-ray shielding ability of this composite. The 3 experimental measurements of the mass attenuation coefficients were compared to the theoretical values tabulated in the NIST databases XCOM and FFAST. The mass attenuation coefficient was increased with the increment of WO 3 wt.% as well as with the decrease of the WO 3 particle size. This improvement in the attenuation parameters of the NP(C) composite suggests their promising applications in radiation protection at the diagnostic level.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"26 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68546938","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}
Milan N. Tanić, Denis Dinić, Ž. Mihaljev, B. Kartalović, M. Daković
This study aims to obtain data on terrestrial radioactivity coming from naturally occurring (40K, 226Ra, 232Th, and 238U) and artificial (137Cs) radionuclides in surface soil (0-10 cm) of selected eighteen public-access urban areas in Krusevac city, Serbia, and to assess the corresponding health effects for citizens using those areas for recreational purposes. The specific activities of investigated radionuclides were analyzed using HPGe gamma-ray spectrometry. The mean specific activity of 40K, 226Ra, 232Th, 238U, and 137Cs was found to be 353, 39.8, 38.9, 41.0, and 5.9, respectively, in compliance with their values in other parts of Serbia and neighboring countries reported in similar researches. To evaluate the human health risk associated with radionuclides, conservative exposure assumptions and models recommended by the United States Environmental Protection Agency were employed taking into account three exposure routes: ingestion, inhalation of soil, and external irradiation. The absorbed gamma dose rate in the air due to natural radionuclides in soil was calculated. The calculated indices suggested that the radiation risk arising from natural and artificial radionuclides was not significant. The total excess lifetime cancer based on the 95 % upper confidence limit of the specific activities mean was calculated to be 5.89?10?6, lower than the tolerable risk for regulatory purposes (10?4). Among investigated radiation exposure pathways, external exposure was the most contributing one for the health risk. The results obtained for the city's parks and playgrounds suggested their safe use for recreational purposes from the radioecological point of view.
{"title":"Risk assessment of human exposure to radionuclides in soil of urban areas (public parks and open playgrounds) in Krusevac, Serbia","authors":"Milan N. Tanić, Denis Dinić, Ž. Mihaljev, B. Kartalović, M. Daković","doi":"10.2298/ntrp2103271t","DOIUrl":"https://doi.org/10.2298/ntrp2103271t","url":null,"abstract":"This study aims to obtain data on terrestrial radioactivity coming from naturally occurring (40K, 226Ra, 232Th, and 238U) and artificial (137Cs) radionuclides in surface soil (0-10 cm) of selected eighteen public-access urban areas in Krusevac city, Serbia, and to assess the corresponding health effects for citizens using those areas for recreational purposes. The specific activities of investigated radionuclides were analyzed using HPGe gamma-ray spectrometry. The mean specific activity of 40K, 226Ra, 232Th, 238U, and 137Cs was found to be 353, 39.8, 38.9, 41.0, and 5.9, respectively, in compliance with their values in other parts of Serbia and neighboring countries reported in similar researches. To evaluate the human health risk associated with radionuclides, conservative exposure assumptions and models recommended by the United States Environmental Protection Agency were employed taking into account three exposure routes: ingestion, inhalation of soil, and external irradiation. The absorbed gamma dose rate in the air due to natural radionuclides in soil was calculated. The calculated indices suggested that the radiation risk arising from natural and artificial radionuclides was not significant. The total excess lifetime cancer based on the 95 % upper confidence limit of the specific activities mean was calculated to be 5.89?10?6, lower than the tolerable risk for regulatory purposes (10?4). Among investigated radiation exposure pathways, external exposure was the most contributing one for the health risk. The results obtained for the city's parks and playgrounds suggested their safe use for recreational purposes from the radioecological point of view.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"16 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68547075","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}
Jelena Stankovic-Petrovic, Ž. Knežević, N. Kržanović, M. Majer, M. Živanović, O. Ciraj-Bjelac
Passive solid state dosimeters, such as thermoluminescence dosimeters, provide integrated measurement of the total dose and are widely used in environmental monitoring programs. The objective of this paper is to provide a comprehensive review on the use of thermoluminescent dosimetry methods for monitoring radiation dose in the environment. The article presents the part of the research results of the project PREPAREDNESS (EMPIR 2016 call for Metrology for Environment joint research project) with a particular objective to harmonize procedures used by dosimetry services, relevant authorities and Institutes across the Europe. To achieve this, different monitoring routines that are based on passive environ mental dosimetry methods are investigated. Differences in performing specific steps such as preheating, reading, annealing, minimizing fading, and others, are analyzed. The investigation was performed by means of qualitative literature review that showed the lack of information about specific steps. The conclusion of this work is that thermoluminescent dosimetry measurement system has to be type-tested even though the testing procedure is complicated. In addition to this, control dosimeters should be introduced, International Organization for Standardization protocols should be followed during calibration, and finally, parameters influencing the measurement uncertainty have to be identified and well understood in order to pro duce ac cu rate dose measurement results.
{"title":"Review of the thermoluminescent dosimetry method for the environmental dose monitoring","authors":"Jelena Stankovic-Petrovic, Ž. Knežević, N. Kržanović, M. Majer, M. Živanović, O. Ciraj-Bjelac","doi":"10.2298/ntrp2102150s","DOIUrl":"https://doi.org/10.2298/ntrp2102150s","url":null,"abstract":"Passive solid state dosimeters, such as thermoluminescence dosimeters, provide integrated measurement of the total dose and are widely used in environmental monitoring programs. The objective of this paper is to provide a comprehensive review on the use of thermoluminescent dosimetry methods for monitoring radiation dose in the environment. The article presents the part of the research results of the project PREPAREDNESS (EMPIR 2016 call for Metrology for Environment joint research project) with a particular objective to harmonize procedures used by dosimetry services, relevant authorities and Institutes across the Europe. To achieve this, different monitoring routines that are based on passive environ mental dosimetry methods are investigated. Differences in performing specific steps such as preheating, reading, annealing, minimizing fading, and others, are analyzed. The investigation was performed by means of qualitative literature review that showed the lack of information about specific steps. The conclusion of this work is that thermoluminescent dosimetry measurement system has to be type-tested even though the testing procedure is complicated. In addition to this, control dosimeters should be introduced, International Organization for Standardization protocols should be followed during calibration, and finally, parameters influencing the measurement uncertainty have to be identified and well understood in order to pro duce ac cu rate dose measurement results.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68546102","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}
The probability of Cs+ and Co2+ ions retention by immobilization processes in the cement matrix was determinate as the subject of analyses: matrix design, water/cement ratio, and structure porosity. Comparison of experimental results was accomplished by Hespe standard leaching method. Diffusion and semi-empirical models were used for the assessment of the washing rate as a function of time. The higher value of cement matrix mechanical resistance corresponds to a lower value of Co2+ and Cs+ ions leaching. Co2+ leaching level was more than two orders of magnitude less than the leaching level of Cs+. The influence of bentonite and zeolite on Co2+ leaching reduction was significantly smaller in comparison with Cs+, while zeolite had a higher Cs+ and Co2+ sorption ability than bentonite. Under static leaching conditions, the contribution of diffusion to the total transport of ions in the matrix porous medium was dominant. The contribution of matrix dissolution was insignificant concerning the dominant contribution of diffusion and surface washing. The semi-empirical model showed a better approximation of the Co2+ and Cs+ ions laboratory leaching process.
{"title":"Influence of bentonite and zeolite on Cs+ and Co2+ cement matrix leaching phenomena","authors":"S. Dimović, I. Jelić, M. Šljivić-Ivanović","doi":"10.2298/ntrp201130003d","DOIUrl":"https://doi.org/10.2298/ntrp201130003d","url":null,"abstract":"The probability of Cs+ and Co2+ ions retention by immobilization processes in the cement matrix was determinate as the subject of analyses: matrix design, water/cement ratio, and structure porosity. Comparison of experimental results was accomplished by Hespe standard leaching method. Diffusion and semi-empirical models were used for the assessment of the washing rate as a function of time. The higher value of cement matrix mechanical resistance corresponds to a lower value of Co2+ and Cs+ ions leaching. Co2+ leaching level was more than two orders of magnitude less than the leaching level of Cs+. The influence of bentonite and zeolite on Co2+ leaching reduction was significantly smaller in comparison with Cs+, while zeolite had a higher Cs+ and Co2+ sorption ability than bentonite. Under static leaching conditions, the contribution of diffusion to the total transport of ions in the matrix porous medium was dominant. The contribution of matrix dissolution was insignificant concerning the dominant contribution of diffusion and surface washing. The semi-empirical model showed a better approximation of the Co2+ and Cs+ ions laboratory leaching process.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68545535","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. Stefanović, Nikola Krunić, Nataša Danilović-Hristić
In the Republic of Serbia, radioactive waste has been stored for many years at the Vinca location near Belgrade. However, the location is not suitable for this purpose. It is necessary to define a location for radioactive waste disposal in Serbia in accordance with international criteria, strict spatial conditions and planning solutions of national interest. The need to conduct research that will define potential zones for radioactive waste disposal is the basic starting point in this paper. The framework of the research is the development of the Spatial Plan of the Republic of Serbia from 2021 to 2035, on the basis of which it is possible to determine potential zones for the construction of a radioactive waste disposal. In this paper, the authors present the results of research on spatial constraints from the aspects of geological and hydrological conditions, spatial protection, and distribution of the population, settlements and buildings, etc. A special contribution it makes is the additional analysis of conditionality in relation to the planned purposes and activities of national and priority importance in Serbia. The collection, processing and presentation of spatial data is the result of analyses conducted with the support of geographic information systems. The research contributes to a definition of potential zones, within the scope of which it is necessary to conduct further research and select the optimal location for a radioactive waste disposal. The paper provides methodological guidelines for further scientific research into the spatial aspects of radioactive waste disposal in Serbia, at the same time pointing out possible directions for further resolution of this issue in practice.
{"title":"The spatial and planning aspect of solving the issue of radioactive waste disposal in the Republic of Serbia","authors":"N. Stefanović, Nikola Krunić, Nataša Danilović-Hristić","doi":"10.2298/ntrp210119011s","DOIUrl":"https://doi.org/10.2298/ntrp210119011s","url":null,"abstract":"In the Republic of Serbia, radioactive waste has been stored for many years at the Vinca location near Belgrade. However, the location is not suitable for this purpose. It is necessary to define a location for radioactive waste disposal in Serbia in accordance with international criteria, strict spatial conditions and planning solutions of national interest. The need to conduct research that will define potential zones for radioactive waste disposal is the basic starting point in this paper. The framework of the research is the development of the Spatial Plan of the Republic of Serbia from 2021 to 2035, on the basis of which it is possible to determine potential zones for the construction of a radioactive waste disposal. In this paper, the authors present the results of research on spatial constraints from the aspects of geological and hydrological conditions, spatial protection, and distribution of the population, settlements and buildings, etc. A special contribution it makes is the additional analysis of conditionality in relation to the planned purposes and activities of national and priority importance in Serbia. The collection, processing and presentation of spatial data is the result of analyses conducted with the support of geographic information systems. The research contributes to a definition of potential zones, within the scope of which it is necessary to conduct further research and select the optimal location for a radioactive waste disposal. The paper provides methodological guidelines for further scientific research into the spatial aspects of radioactive waste disposal in Serbia, at the same time pointing out possible directions for further resolution of this issue in practice.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68545566","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}
Ljiljana M. Kljajević, M. Mirković, S. Dolenec, Katarina Šter, M. Hadžalić, I. Vukanac, M. Nenadovic
The potential re-use of red mud in the building and construction industry has been the subject of research of many scientists. The presented research is a contribution to the potential solution of this environmental issue through the synthesis of potential construction materials based on red mud. A promising way of recycling these secondary raw materials is the synthesis of alkali-activated binders or alkali activated materials. Alkali-activated materials or inorganic binders based on red mud are a new class of materials obtained by activation of inorganic precursors mainly constituted by silica, alumina and low content of calcium oxide. Since red mud contains radioactive elements like 226Ra and 232Th, this may be a problem for its further utilization. The content of naturally occurring radionuclides in manufactured material products with potential application in the building and construction industry is important from the standpoint of radiation protection. Gamma radiation of the primordial radionuclides, 40K and members of the uranium and thorium series, increases the external gamma dose rate. However, more and more precedence is being given to limiting the radiological dose originating from building materials on the population these days. The aim of this research was to investigate the possible influence of alkali activation-polymerization processes on the natural radioactivity of alkali activated materials synthesized by red mud (BOKSIT a. d. Milici, Zvornik, Bosnia and Herzegovina) and their structural properties. This research confirmed that during the polymerization process the natural radioactivity was reduced, and that the process of alkali activation of raw materials has an influence on natural radioactivity of synthesized materials.
{"title":"Radiological and physico-chemical characterization of red mud as an Al-containing precursor in inorganic binders for the building industry","authors":"Ljiljana M. Kljajević, M. Mirković, S. Dolenec, Katarina Šter, M. Hadžalić, I. Vukanac, M. Nenadovic","doi":"10.2298/ntrp2102182k","DOIUrl":"https://doi.org/10.2298/ntrp2102182k","url":null,"abstract":"The potential re-use of red mud in the building and construction industry has been the subject of research of many scientists. The presented research is a contribution to the potential solution of this environmental issue through the synthesis of potential construction materials based on red mud. A promising way of recycling these secondary raw materials is the synthesis of alkali-activated binders or alkali activated materials. Alkali-activated materials or inorganic binders based on red mud are a new class of materials obtained by activation of inorganic precursors mainly constituted by silica, alumina and low content of calcium oxide. Since red mud contains radioactive elements like 226Ra and 232Th, this may be a problem for its further utilization. The content of naturally occurring radionuclides in manufactured material products with potential application in the building and construction industry is important from the standpoint of radiation protection. Gamma radiation of the primordial radionuclides, 40K and members of the uranium and thorium series, increases the external gamma dose rate. However, more and more precedence is being given to limiting the radiological dose originating from building materials on the population these days. The aim of this research was to investigate the possible influence of alkali activation-polymerization processes on the natural radioactivity of alkali activated materials synthesized by red mud (BOKSIT a. d. Milici, Zvornik, Bosnia and Herzegovina) and their structural properties. This research confirmed that during the polymerization process the natural radioactivity was reduced, and that the process of alkali activation of raw materials has an influence on natural radioactivity of synthesized materials.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68546165","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}
The value of personal dose equivalent at10 mm depth is to characterize the energy deposition of strong penetrating radiation in human body and is derived by measurement of air kerma and application of conversion coefficients from ISO report. However, the conversion coefficients depend strongly on the photon energy and angles of incidence for low-energy photons. In order to overcome the problem that the conversion coefficient of low energy rays changes greatly due to the small change of energy, a secondary standard ionization chamber was used to measure personal dose equivalent directly. A matched reference field was established with (20-250) kV X-rays and correction factors with Hp(10) chamber were calculated under these radiation qualities with different angles of incidence. The results showed that the differences were almost 22.7 % of correction factors for the low energy photons at angles of incidence 0?. With conversion coefficient recommended in ISO 4037-3-2019, performance of the chamber response with respect to Hp(10) in the energy range from 33 keV to 208 keV was within about ?10%, and in the energy range from 12 keV to 208 keV and for angles of incidence between 0? and 75? was within about ?19%.
{"title":"Calibration and measurement of X-ray personal dose equivalent with a Hp(10) ionization chamber","authors":"Yang Xu, Rui Zhao","doi":"10.2298/ntrp210304019x","DOIUrl":"https://doi.org/10.2298/ntrp210304019x","url":null,"abstract":"The value of personal dose equivalent at10 mm depth is to characterize the energy deposition of strong penetrating radiation in human body and is derived by measurement of air kerma and application of conversion coefficients from ISO report. However, the conversion coefficients depend strongly on the photon energy and angles of incidence for low-energy photons. In order to overcome the problem that the conversion coefficient of low energy rays changes greatly due to the small change of energy, a secondary standard ionization chamber was used to measure personal dose equivalent directly. A matched reference field was established with (20-250) kV X-rays and correction factors with Hp(10) chamber were calculated under these radiation qualities with different angles of incidence. The results showed that the differences were almost 22.7 % of correction factors for the low energy photons at angles of incidence 0?. With conversion coefficient recommended in ISO 4037-3-2019, performance of the chamber response with respect to Hp(10) in the energy range from 33 keV to 208 keV was within about ?10%, and in the energy range from 12 keV to 208 keV and for angles of incidence between 0? and 75? was within about ?19%.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68546827","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}
The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce rod-type fuel. Calculating the safety parameters and their reliability related to reactor operation has become an important thing to do. The objective of this study was to perform the reactor transient calculation of TRIGA 2000 that uses plate-type fuel. The reactor core modification is based on the capability of the existing primary coolant system, without changing its flow rates. Thermal-hydraulics calculations related to reactivity insertion accident and loss of flow accident were analyzed using EUREKA2/RR, MTR-DYN, and RELAP5 codes. The chosen loss of flow accident scenario is a decrease in flow caused by a sudden stop of the pump power supply, while reactivity insertion accident is conducted by the withdrawal of control rods with maximum reactivity insertion of 32.33 ? 10?5 s?1. The calculated parameters are reactivity, reactor power, and temperature of the coolant, cladding, and fuel in the hottest channel position. In general, from a safety point of view, those computer codes were capable of performing the transient calculations with appropriate results. Based on the calculation results, during the transient condition of both reactivity insertion accident and loss of flow accident scenario, the reactor operation safety parameters do not exceed the allowable safety limit.
万隆TRIGA 2000反应堆被提议从棒型燃料转换为板型燃料，因为世界上没有制造商仍然生产棒型燃料。计算与反应堆运行有关的安全参数及其可靠性已成为一项重要的工作。本研究的目的是对使用板型燃料的TRIGA 2000进行反应堆瞬态计算。反应堆堆芯的改造是基于现有主冷却剂系统的能力，而不改变其流量。使用EUREKA2/RR、MTR-DYN和RELAP5代码分析与反应性插入事故和失流事故相关的热工力学计算。所选择的失流事故场景是由于泵的电源突然停止导致流量减少，而反应性插入事故是由于控制棒的拔出造成的，反应性插入的最大值为32.33 ?10？5 s ? 1。计算的参数包括反应性、反应堆功率、冷却剂、包层和最热通道位置燃料的温度。一般来说，从安全的角度来看，这些计算机代码能够进行瞬态计算并得到适当的结果。计算结果表明，在反应性插入事故和失流事故两种暂态工况下，反应堆运行安全参数均未超过允许的安全限值。
{"title":"Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes","authors":"S. Dibyo, S. Pinem, S. Widodo","doi":"10.2298/ntrp2103211d","DOIUrl":"https://doi.org/10.2298/ntrp2103211d","url":null,"abstract":"The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce rod-type fuel. Calculating the safety parameters and their reliability related to reactor operation has become an important thing to do. The objective of this study was to perform the reactor transient calculation of TRIGA 2000 that uses plate-type fuel. The reactor core modification is based on the capability of the existing primary coolant system, without changing its flow rates. Thermal-hydraulics calculations related to reactivity insertion accident and loss of flow accident were analyzed using EUREKA2/RR, MTR-DYN, and RELAP5 codes. The chosen loss of flow accident scenario is a decrease in flow caused by a sudden stop of the pump power supply, while reactivity insertion accident is conducted by the withdrawal of control rods with maximum reactivity insertion of 32.33 ? 10?5 s?1. The calculated parameters are reactivity, reactor power, and temperature of the coolant, cladding, and fuel in the hottest channel position. In general, from a safety point of view, those computer codes were capable of performing the transient calculations with appropriate results. Based on the calculation results, during the transient condition of both reactivity insertion accident and loss of flow accident scenario, the reactor operation safety parameters do not exceed the allowable safety limit.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68546855","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}
Marko Drasler, I. Čeliković, A. Kandić, G. Pantelić, T. Milanović, A. Samolov, B. Lončar
This paper aims to estimate a potential radiological risk from different kinds of coals used for domestic heating in Serbia, by measuring the activity concentration of radionuclides and radon exhalation rate. The obtained radon mass exhalation rate ranges from (5.3 ? 3.1) mBqkg?1s?1 to (70.3 ? 9.4) mBqkg ?1s?1 and was highest for lignite type of coal. It is estimated that coal stored in the basement could contribute up to 50 Bqm?3 of indoor radon concentration at the ground level. Activity concentrations of 226Ra, 232Th, 40K, 238U, 235U, and 210Pb in analysed coal samples agree with previously reported concentrations of coal used in Serbia. The values of radium equivalent concentration and external hazard index indicate that the used coal does not represent a significant radiation hazard.
本文旨在通过测量放射性核素的活性浓度和氡的呼出率，估计塞尔维亚用于家庭供暖的不同种类煤的潜在辐射风险。得到的氡质量呼出率范围为(5.3 ?3.1) mBqkg 1 s ?1到70.3 ?9.4) mBqkg ?1，以褐煤型煤最高。据估计，储存在地下室的煤可以贡献高达50立方英尺/立方米的能量。3 .室内地面氡浓度。分析的煤样品中226Ra、232Th、40K、238U、235U和210Pb的活性浓度与以前报道的塞尔维亚使用的煤浓度一致。镭当量浓度和外部危害指数表明，废煤不存在显著的辐射危害。
{"title":"Estimation of radiological impact on residents due to household storage of coal used for heating in Serbia","authors":"Marko Drasler, I. Čeliković, A. Kandić, G. Pantelić, T. Milanović, A. Samolov, B. Lončar","doi":"10.2298/ntrp2103284d","DOIUrl":"https://doi.org/10.2298/ntrp2103284d","url":null,"abstract":"This paper aims to estimate a potential radiological risk from different kinds of coals used for domestic heating in Serbia, by measuring the activity concentration of radionuclides and radon exhalation rate. The obtained radon mass exhalation rate ranges from (5.3 ? 3.1) mBqkg?1s?1 to (70.3 ? 9.4) mBqkg ?1s?1 and was highest for lignite type of coal. It is estimated that coal stored in the basement could contribute up to 50 Bqm?3 of indoor radon concentration at the ground level. Activity concentrations of 226Ra, 232Th, 40K, 238U, 235U, and 210Pb in analysed coal samples agree with previously reported concentrations of coal used in Serbia. The values of radium equivalent concentration and external hazard index indicate that the used coal does not represent a significant radiation hazard.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68547138","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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