M. Nenadovic, C. Ferone, Ljiljana M. Kljajević, M. Mirković, B. Todorović, I. Vukanac, S. Nenadović
Presented study deals with the final structure and radiological properties of different fly ash-based geopolymers. lignite fly-ash (lignite Kolubara - Serbia) and wood fly ash were obtained in combustion process together with commercial fly ash. Synthesis of the geopolymers was conducted by mixing fly ash, sodium silicate solution, NaOH and water. The samples were cured at 60?C for 48h after staying at room temperature in covering mold for 24 h. X - ray diffraction, Fourier transform infra - red and Scanning electron microscope measurements were conducted on the samples after 28 days of geopolymerization process. X-ray diffraction measurements of lignite fly ash samples show anhydrite as the main constituent, while wood fly ash samples consist of calcite, albite and gypsum minerals. Beside of determination of physical-chemical properties, the aim of this study was radiological characterization of lignite fly ash, wood fly ash and the obtained geopolymer products. Activity concentration of 40K and radionuclides from the 238U and 232Th decay series in ash samples and fly ash-based geopolymers were determined by means of gamma-ray spectrometry, and the absorbed dose rate rate (D) and the annual effective dose rate (E) were calculated in accordance with the UNSCEAR 2000 report.
{"title":"Alkali activation of different type of ash as a production of combustion process","authors":"M. Nenadovic, C. Ferone, Ljiljana M. Kljajević, M. Mirković, B. Todorović, I. Vukanac, S. Nenadović","doi":"10.2298/ntrp201120006n","DOIUrl":"https://doi.org/10.2298/ntrp201120006n","url":null,"abstract":"Presented study deals with the final structure and radiological properties of different fly ash-based geopolymers. lignite fly-ash (lignite Kolubara - Serbia) and wood fly ash were obtained in combustion process together with commercial fly ash. Synthesis of the geopolymers was conducted by mixing fly ash, sodium silicate solution, NaOH and water. The samples were cured at 60?C for 48h after staying at room temperature in covering mold for 24 h. X - ray diffraction, Fourier transform infra - red and Scanning electron microscope measurements were conducted on the samples after 28 days of geopolymerization process. X-ray diffraction measurements of lignite fly ash samples show anhydrite as the main constituent, while wood fly ash samples consist of calcite, albite and gypsum minerals. Beside of determination of physical-chemical properties, the aim of this study was radiological characterization of lignite fly ash, wood fly ash and the obtained geopolymer products. Activity concentration of 40K and radionuclides from the 238U and 232Th decay series in ash samples and fly ash-based geopolymers were determined by means of gamma-ray spectrometry, and the absorbed dose rate rate (D) and the annual effective dose rate (E) were calculated in accordance with the UNSCEAR 2000 report.","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":"68544984","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}
Teodora Nedić, D. Lazarevic, K. Stanković, N. Kartalović
This paper considered the possibility of reducing the dissipation of the trigger time of the three-electrode spark gaps with a separated triggered electrode. The work is of a theoretical, numerical and of experimental nature. The experiments were performed on a spark gap model under well-controlled laboratory conditions. It was determined that the results obtained with the model can be applied to the spark gap prototype. Unlike the previous research in this area, the computer-designed spark gap that was used can be triggered with one mechanism only. Also, as opposed to the previous study, a mixture of SF6 and He gases and the third electrode with a double ionization effect were used. The obtained results showed the optimal combination of the construction solution, insulation gas, triggered impulse, and the triggered electrode's shape, reduce the stochastic dissipation of a random variable far in the sub-microsecond field. This result is of great significance for the parallel triggering of current and voltage generators to obtain the best superposition signals.
{"title":"Optimization of fast three-electrode spark gaps isolated with a SF6 and he mixture","authors":"Teodora Nedić, D. Lazarevic, K. Stanković, N. Kartalović","doi":"10.2298/ntrp2103234n","DOIUrl":"https://doi.org/10.2298/ntrp2103234n","url":null,"abstract":"This paper considered the possibility of reducing the dissipation of the trigger time of the three-electrode spark gaps with a separated triggered electrode. The work is of a theoretical, numerical and of experimental nature. The experiments were performed on a spark gap model under well-controlled laboratory conditions. It was determined that the results obtained with the model can be applied to the spark gap prototype. Unlike the previous research in this area, the computer-designed spark gap that was used can be triggered with one mechanism only. Also, as opposed to the previous study, a mixture of SF6 and He gases and the third electrode with a double ionization effect were used. The obtained results showed the optimal combination of the construction solution, insulation gas, triggered impulse, and the triggered electrode's shape, reduce the stochastic dissipation of a random variable far in the sub-microsecond field. This result is of great significance for the parallel triggering of current and voltage generators to obtain the best superposition signals.","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":"68546695","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}
A determination option for 238U in solutions by the neutron activation analysis was investigated. A radionuclide treatment based on 252Cf was used as a neutron source. The limit for the determination of uranium using thermal neutrons of 0.1 mg L-1 was determined within the research framework. With the help of preliminary concentration of the sample via the evaporation method, it is possible to further reduce the detection limit by 2-5 times. It is defined that the optimal time for measuring the induced activity of the sample, when working with a short-life isotope of 239U, is 30 min. The influence of the effects of scattering and self-absorption of gamma radiation of the uranium line 74.6 keV on the results of the neutron activation analysis is determined. The studies conducted made it possible to determine uranium by the neutron activation analysis method in solutions of various compositions, in a wide range of concentrations.
{"title":"Determination uranium in solutions by the method of neutron activation analysis with 252Cf radionuclide neutron source","authors":"I. S. Ivannikov, S. Markin, V. Zheleznov","doi":"10.2298/ntrp201217005i","DOIUrl":"https://doi.org/10.2298/ntrp201217005i","url":null,"abstract":"A determination option for 238U in solutions by the neutron activation analysis was investigated. A radionuclide treatment based on 252Cf was used as a neutron source. The limit for the determination of uranium using thermal neutrons of 0.1 mg L-1 was determined within the research framework. With the help of preliminary concentration of the sample via the evaporation method, it is possible to further reduce the detection limit by 2-5 times. It is defined that the optimal time for measuring the induced activity of the sample, when working with a short-life isotope of 239U, is 30 min. The influence of the effects of scattering and self-absorption of gamma radiation of the uranium line 74.6 keV on the results of the neutron activation analysis is determined. The studies conducted made it possible to determine uranium by the neutron activation analysis method in solutions of various compositions, in a wide range of concentrations.","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":"68545763","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}
P. Vukotic, M. N. Antovic, R. Zekić, A. Djurovic, Tomislav Andjelić, N. Svrkota, R. Mrdak, A. Dlabac
After year-long measurements with CR-39 detectors, nationwide radon survey was performed in 953 homes - 0.5% of all permanently inhabited dwellings in Montenegro. Influence of 11 factors (area, climate, type of house, year of construction, basement, foundation slab, number of stories, building materials, window frames, heating and smoking) and 35 their categories on the radon concentrations in 732 ground-floor dwellings was analyzed using descriptive, univariate and multivariate methods. Univariate analysis dropped influence of the two factors - heating and smoking. It reveals that, on average, radon concentrations in ground-floor dwellings differ at 95% confidence level in urban and rural areas, in family houses and apartment buildings, in houses with and without basement, and in dwellings with window frames made of wood and PVC/Al. In Cf climate zone they differ from those in Cs and Df zones. Only two pairs of construction periods differ in mean radon concentrations in dwellings: 1980-1999 with 1900-1944, and with 1964-1979. Houses with one, two or three stories have almost equal average radon levels, which are higher than in buildings with more than three stories. Mean value of radon concentrations in houses made of stone are higher than in houses made of concrete, or bricks, or wood. Multivariate analysis revealed that six of the analyzed factors - area, climate, type of house, presence of basement, number of stories and building materials simultaneously have significant relationships (p < 0.05) with radon concentrations in dwellings on ground floor in Montenegro.
{"title":"Influence of climate, building and residential factors on radon levels in ground-floor dwellings in Montenegro","authors":"P. Vukotic, M. N. Antovic, R. Zekić, A. Djurovic, Tomislav Andjelić, N. Svrkota, R. Mrdak, A. Dlabac","doi":"10.2298/ntrp201225012v","DOIUrl":"https://doi.org/10.2298/ntrp201225012v","url":null,"abstract":"After year-long measurements with CR-39 detectors, nationwide radon survey was performed in 953 homes - 0.5% of all permanently inhabited dwellings in Montenegro. Influence of 11 factors (area, climate, type of house, year of construction, basement, foundation slab, number of stories, building materials, window frames, heating and smoking) and 35 their categories on the radon concentrations in 732 ground-floor dwellings was analyzed using descriptive, univariate and multivariate methods. Univariate analysis dropped influence of the two factors - heating and smoking. It reveals that, on average, radon concentrations in ground-floor dwellings differ at 95% confidence level in urban and rural areas, in family houses and apartment buildings, in houses with and without basement, and in dwellings with window frames made of wood and PVC/Al. In Cf climate zone they differ from those in Cs and Df zones. Only two pairs of construction periods differ in mean radon concentrations in dwellings: 1980-1999 with 1900-1944, and with 1964-1979. Houses with one, two or three stories have almost equal average radon levels, which are higher than in buildings with more than three stories. Mean value of radon concentrations in houses made of stone are higher than in houses made of concrete, or bricks, or wood. Multivariate analysis revealed that six of the analyzed factors - area, climate, type of house, presence of basement, number of stories and building materials simultaneously have significant relationships (p < 0.05) with radon concentrations in dwellings on ground floor in Montenegro.","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":"68545904","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}
R. Havránková, Eva Simackova, F. Zolzer, J. Havránek, Z. Freitinger-Skalicka
This study presents measurements of activity concentrations of natural radionuclides in selected water and soil samples taken from areas affected by the uranium industry in the surroundings of Pribram, Straz pod Ralskem and Mydlovary, Czech Republic. In these areas, the dose equivalent rate was also determined at the sampling locations and additionally also during walkabouts in the surroundings of sludge fields. The activity concentration of water samples was 0.06 ? 0.02 BqL?1 for 226Ra and 0.07 ? 0.07 mgL?1 for 238U while the mean activity concentrations of soil samples were 74 ? 70 Bqkg?1 and 80 ? 77 Bqkg?1 for 226Ra and 238U, respectively. The average value of the dose equivalent rate was of 0.15 ? 0.1 ?Svh?1. These values conform with the nature of the industrial activities which were carried out in the areas and are comparable with measurement results in similar locations worldwide.
{"title":"Assessment of the radiological situation in different areas affected by uranium mining and uranium processing in the Czech Republic","authors":"R. Havránková, Eva Simackova, F. Zolzer, J. Havránek, Z. Freitinger-Skalicka","doi":"10.2298/ntrp2102139h","DOIUrl":"https://doi.org/10.2298/ntrp2102139h","url":null,"abstract":"This study presents measurements of activity concentrations of natural radionuclides in selected water and soil samples taken from areas affected by the uranium industry in the surroundings of Pribram, Straz pod Ralskem and Mydlovary, Czech Republic. In these areas, the dose equivalent rate was also determined at the sampling locations and additionally also during walkabouts in the surroundings of sludge fields. The activity concentration of water samples was 0.06 ? 0.02 BqL?1 for 226Ra and 0.07 ? 0.07 mgL?1 for 238U while the mean activity concentrations of soil samples were 74 ? 70 Bqkg?1 and 80 ? 77 Bqkg?1 for 226Ra and 238U, respectively. The average value of the dose equivalent rate was of 0.15 ? 0.1 ?Svh?1. These values conform with the nature of the industrial activities which were carried out in the areas and are comparable with measurement results in similar locations worldwide.","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":"68546048","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}
Qing-Hua He, Tian Li, Xiao-Suo He, Kai-Kai Lu, Sheng-Kai Wang
When verifying the authenticity for nuclear warheads dismantlement toward a treaty partner's obligation, nuclear arms verification technologies are critical since only nuclear disarmament treaties are not sufficient to neutralize the existential threat of nuclear weapons. In this work, we present a verification method combining a numerical observer model and physical encryption techniques. The performance of the method is quantified by Monte Carlo simulations with several typical deception scenarios. Simulation results show this method can efficiently complete identification tasks in the presence of noise (<5 %) and source-term variability, meanwhile exhibiting high security against brute-force attacks which reconstruct detection data by the exhaustive method.
{"title":"A physically cryptographic hoteling observer for nuclear warhead verification","authors":"Qing-Hua He, Tian Li, Xiao-Suo He, Kai-Kai Lu, Sheng-Kai Wang","doi":"10.2298/ntrp2104358h","DOIUrl":"https://doi.org/10.2298/ntrp2104358h","url":null,"abstract":"When verifying the authenticity for nuclear warheads dismantlement toward a treaty partner's obligation, nuclear arms verification technologies are critical since only nuclear disarmament treaties are not sufficient to neutralize the existential threat of nuclear weapons. In this work, we present a verification method combining a numerical observer model and physical encryption techniques. The performance of the method is quantified by Monte Carlo simulations with several typical deception scenarios. Simulation results show this method can efficiently complete identification tasks in the presence of noise (<5 %) and source-term variability, meanwhile exhibiting high security against brute-force attacks which reconstruct detection data by the exhaustive method.","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":"68547630","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 paper presents results of electrical breakdown time delay mean value t?d as a function of relaxation time ? (memory curve) for krypton and xenon-filled diodes at 270 Pa pressure. Memory curves were obtained for the cases without radiation as well as in the presence of gamma and UV radiation. It was shown that significant influence of UV radiation to t?d can be observed for ? ? 100 ms, as well as gamma radiation for ? ? 103 ms. Laue's distribution was also investigated for electrical breakdown time delay data sets td, obtained for ? ? 150 ms, without radiation as well as in the presence of gamma and UV radiation. It was shown that for all these data sets Laue's distribution stands, except for the case when krypton-filled tube was subjected to UV radiation. On the basis of the obtained results, the throughout analysis was performed with the aim to investigate possible application of these diodes as sensors of gamma and UV radiation.
{"title":"The possibility for gamma and UV radiation detection based on electrical breakdown time delay measurement in krypton and xenon filled diodes","authors":"M. Pejović, E. Živanović, Čedomir Belić","doi":"10.2298/ntrp2103243p","DOIUrl":"https://doi.org/10.2298/ntrp2103243p","url":null,"abstract":"The paper presents results of electrical breakdown time delay mean value t?d as a function of relaxation time ? (memory curve) for krypton and xenon-filled diodes at 270 Pa pressure. Memory curves were obtained for the cases without radiation as well as in the presence of gamma and UV radiation. It was shown that significant influence of UV radiation to t?d can be observed for ? ? 100 ms, as well as gamma radiation for ? ? 103 ms. Laue's distribution was also investigated for electrical breakdown time delay data sets td, obtained for ? ? 150 ms, without radiation as well as in the presence of gamma and UV radiation. It was shown that for all these data sets Laue's distribution stands, except for the case when krypton-filled tube was subjected to UV radiation. On the basis of the obtained results, the throughout analysis was performed with the aim to investigate possible application of these diodes as sensors of gamma and UV radiation.","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":"68546812","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}
B. Petrovic, D. Faj, Mladen Markovic, A. Tot, M. Marjanović, Mladen Kasabašić, I. Gencel, Dragomir Paunovic, J. Stankovic, Jelena Krestić-Vesović, Ivana Mišković, Koca Cicarevic, Juraj Bibić, M. Budanec, I. Králik, S. Galic, Darijo Hrepić, Lejla Ibrisimovic, Jasna Davidović, G. Kolarević
The purpose of this work was to evaluate computed tomography (CT) simulators used in radiotherapy treatment planning in Serbia, Croatia and Bosnia and Herzegovina. A survey of quality assurance programmes of 24 CT simulators in 16 facilities was conducted. Dedicated CT-to-ED phantom was scanned at 120 kV and 140 kV, to obtain CT-to-ED (ED- Electron Density) conversion curves as well as CTDIvol. Thoracal phantoms were scanned in standard and extended field of view to evaluate dosimetric effect on treatment planning and delivery. Mean age of measured scanners was 5.5 years. The mean water HU value was -6.5 (all scanners, all voltages) and air HU value was -997. Extended field of view CT data differ from standard field of view and differences between conversion curves have significant dosimetric impact. The CTDI data showed large range of values between centers. Better QA of CT simulators in all countries is recommended. CT-to-ED curve could be used as default at one voltage and per manufacturer. Extended field of view imaging can be used, but treatment planning should be avoided in the regions out of standard field of view.
这项工作的目的是评估在塞尔维亚，克罗地亚和波斯尼亚和黑塞哥维那放射治疗计划中使用的计算机断层扫描(CT)模拟器。对16个设施的24台CT模拟器的质量保证计划进行了调查。在120 kV和140 kV下扫描专用CT-to-ED模体，获得CT-to-ED (ED- Electron Density)转换曲线和CTDIvol。在标准视场和扩展视场扫描胸廓幻象，评估剂量学对治疗计划和给药的影响。所测扫描仪的平均年龄为5.5岁。水中平均HU值为-6.5(所有扫描仪，所有电压)，空气平均HU值为-997。扩展视场CT数据不同于标准视场，转换曲线之间的差异具有显著的剂量学影响。CTDI数据显示中心之间的数值范围较大。建议各国对CT模拟器进行更好的质量保证。ct - ed曲线可以作为一个电压和每个制造商的默认值。可采用扩展视场成像，但应避免在标准视场外的区域进行治疗计划。
{"title":"Assessment of ct simulators used in radiotherapy treatment planning in Serbia, Croatia and Bosnia and Herzegovina","authors":"B. Petrovic, D. Faj, Mladen Markovic, A. Tot, M. Marjanović, Mladen Kasabašić, I. Gencel, Dragomir Paunovic, J. Stankovic, Jelena Krestić-Vesović, Ivana Mišković, Koca Cicarevic, Juraj Bibić, M. Budanec, I. Králik, S. Galic, Darijo Hrepić, Lejla Ibrisimovic, Jasna Davidović, G. Kolarević","doi":"10.2298/ntrp201118009p","DOIUrl":"https://doi.org/10.2298/ntrp201118009p","url":null,"abstract":"The purpose of this work was to evaluate computed tomography (CT) simulators used in radiotherapy treatment planning in Serbia, Croatia and Bosnia and Herzegovina. A survey of quality assurance programmes of 24 CT simulators in 16 facilities was conducted. Dedicated CT-to-ED phantom was scanned at 120 kV and 140 kV, to obtain CT-to-ED (ED- Electron Density) conversion curves as well as CTDIvol. Thoracal phantoms were scanned in standard and extended field of view to evaluate dosimetric effect on treatment planning and delivery. Mean age of measured scanners was 5.5 years. The mean water HU value was -6.5 (all scanners, all voltages) and air HU value was -997. Extended field of view CT data differ from standard field of view and differences between conversion curves have significant dosimetric impact. The CTDI data showed large range of values between centers. Better QA of CT simulators in all countries is recommended. CT-to-ED curve could be used as default at one voltage and per manufacturer. Extended field of view imaging can be used, but treatment planning should be avoided in the regions out of standard field of view.","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":"68545340","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}
Deployment of digital technologies within a modern shift in cyber defense systems is essential for protecting the energy production units. One of the important components of defense is cyberforensics: once an attack has been detected to locate its origin. In this paper, a review of well-known cyberattacks in nuclear facilities is provided, with the lessons learned leading to the development of a machine learning approach implementing identification of internal at- tacks in the facility's data networks. Our approach may be seen as one of the layers in a defense-in-depth strategy that identifies if the attack comes from inside, which may result in identifying faster the attacker's origin. The presented model exploits network packet examination to cast accurate predictions on detailing the origin of malicious network connections. The approach fuses multiple mathematical functions within an artificial neural network to provide a response in the form of 0/1, i. e., whether the attack is identified as internal or not. The utilization of a variety of test cases is developed to explore the relevance and validity of the predictive approach. The proposed implementation is examined with network data packet variance, and the results obtained exhibit a highly accurate detection rate.
{"title":"Review of internal cyber attacks in nuclear facilities and an artificial neural network model for implementing internal cyberforensics","authors":"Brandyn M. Campos, M. Alamaniotis","doi":"10.2298/ntrp2102128c","DOIUrl":"https://doi.org/10.2298/ntrp2102128c","url":null,"abstract":"Deployment of digital technologies within a modern shift in cyber defense systems is essential for protecting the energy production units. One of the important components of defense is cyberforensics: once an attack has been detected to locate its origin. In this paper, a review of well-known cyberattacks in nuclear facilities is provided, with the lessons learned leading to the development of a machine learning approach implementing identification of internal at- tacks in the facility's data networks. Our approach may be seen as one of the layers in a defense-in-depth strategy that identifies if the attack comes from inside, which may result in identifying faster the attacker's origin. The presented model exploits network packet examination to cast accurate predictions on detailing the origin of malicious network connections. The approach fuses multiple mathematical functions within an artificial neural network to provide a response in the form of 0/1, i. e., whether the attack is identified as internal or not. The utilization of a variety of test cases is developed to explore the relevance and validity of the predictive approach. The proposed implementation is examined with network data packet variance, and the results obtained exhibit a highly accurate detection rate.","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":"68546020","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}
Khondokar Sakib Nazmus, Abu Haydar, I. Ali, Debasish Paul, S. Alam
Disposal of radioactive wastes has been emerged as a vital issue for Bangladesh as the country is actively working to be the nuclear power plant operating country by 2023-2024. Current study aims to find out potential sites for a near-surface disposal facility using geographic information system software and multi-criteria analysis method. Previously six regions (Region-1 to Region-6) were identified upon performing continental scale screening over the whole territory of Bangladesh. In the current study, regional scale screening has been performed over the Region-1 and Region-2 using five criteria divided into fifteen sub-criteria, namely earthquakes, wind speed, rainfall, cultivated-vegetated land, forests, buildings-facilities-build up areas (area), buildings-facilities-Industries-institutions (Point), population density, medium-broad road and railway, narrow road, power line, ground water table, surface water body and lastly flood were used in the analysis. The suitability map and relative importance weighting of these sub-criteria were determined by using geographic information system and multi-criteria analysis method. The overlay analysis was performed over suitability maps of each sub-criterion and found final suitability map of the Region-1 and Region-2. These suitability maps were divided into six category, namely excluded area, most suitable, suitable, moderately suitable, unsuitable and completely unsuitable. Nineteen potential sites with maximum and minimum area of 7.90 km2 and 1.15 km2 were identified from these most suitable and suitable areas. Detailed field investigation and site characterization are needed to be performed on selected potential sites to choose a final disposal site for the low and intermediate levels of radioactive waste.
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