Commercial multi-channel energy spectrometers have good performance, they have multiple input signal channels and multi-channel analyzers, which can simultaneously acquire the energy spectrum of multiple nuclear pulse signals. But the input signal channel of this general multi-channel energy spectrometer cannot be switched between the internal multi-channel analyzers, and an input signal channel can only be fixed to the corresponding multi-channel analyzers. Hence, to resolve this issue, this paper designed a nuclear pulse signal array switching circuit. The core of the array switching circuit is a switch array chip with low internal resistance and high bandwidth, which controls the signal connection between the input signal channel with the multi-channel analyzers. Using 137Cs and uranium ore as radioactive sources, the energy spectrum test and spectrum data analysis were carried out using a NaI detector, respectively, when the nuclear pulse signal passed through and did not pass through the array switching circuit. The results showed that the circuit demonstrates little effect on the energy resolution and linearity of the multi-channel analyzers but causes a small drift of the high-energy photopeak, and improve the reliability of the circuit by energy spectrum data accumulation. This circuit can make the application of a multi-channel energy spectrometers more flexible and reliable.
{"title":"Design of array switching circuit for multiplex nuclear pulse signal","authors":"Qi Liu, Haitao Wang, Hailei Chen, Ren-Bo Wang","doi":"10.2298/ntrp2204321l","DOIUrl":"https://doi.org/10.2298/ntrp2204321l","url":null,"abstract":"Commercial multi-channel energy spectrometers have good performance, they have multiple input signal channels and multi-channel analyzers, which can simultaneously acquire the energy spectrum of multiple nuclear pulse signals. But the input signal channel of this general multi-channel energy spectrometer cannot be switched between the internal multi-channel analyzers, and an input signal channel can only be fixed to the corresponding multi-channel analyzers. Hence, to resolve this issue, this paper designed a nuclear pulse signal array switching circuit. The core of the array switching circuit is a switch array chip with low internal resistance and high bandwidth, which controls the signal connection between the input signal channel with the multi-channel analyzers. Using 137Cs and uranium ore as radioactive sources, the energy spectrum test and spectrum data analysis were carried out using a NaI detector, respectively, when the nuclear pulse signal passed through and did not pass through the array switching circuit. The results showed that the circuit demonstrates little effect on the energy resolution and linearity of the multi-channel analyzers but causes a small drift of the high-energy photopeak, and improve the reliability of the circuit by energy spectrum data accumulation. This circuit can make the application of a multi-channel energy spectrometers more flexible and reliable.","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":"68550426","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}
This study presents neutronic analyses of a small modular reactor utilizing transuranium and thorium. Two different fuel cases are considered in the analyses as the transuranium extracted from PWR-MOX spent fuel (a form of a mixture of minor actinide and Pu isotopes) (Case A) and 4.5 % enriched UO2 with ThO 2(the form of separate fuel rods) (Case B). The total power of the considered small modular reactor containing 69 assemblies is 450 MW thermal. In both fuel cases, the time-dependent critical burnup calculations are carried out by using MCNPX 2.7 code until their effective neutron multiplication factors decrease to 0.99. The calculations bring out that the small modular reactor can operate for quite a long time without refueling and that a new fuel with a richness of 1.05 % can be obtained from ThO as well 2 as energy production.
{"title":"Analysis of thorium and transuranium utilization in a small modular reactor","authors":"Gizem Bakir","doi":"10.2298/ntrp2203175b","DOIUrl":"https://doi.org/10.2298/ntrp2203175b","url":null,"abstract":"This study presents neutronic analyses of a small modular reactor utilizing transuranium and thorium. Two different fuel cases are considered in the analyses as the transuranium extracted from PWR-MOX spent fuel (a form of a mixture of minor actinide and Pu isotopes) (Case A) and 4.5 % enriched UO2 with ThO 2(the form of separate fuel rods) (Case B). The total power of the considered small modular reactor containing 69 assemblies is 450 MW thermal. In both fuel cases, the time-dependent critical burnup calculations are carried out by using MCNPX 2.7 code until their effective neutron multiplication factors decrease to 0.99. The calculations bring out that the small modular reactor can operate for quite a long time without refueling and that a new fuel with a richness of 1.05 % can be obtained from ThO as well 2 as energy production.","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":"68548873","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. Kartalović, Alija Jusić, A. Zigic, Dušan P. Nikezić
Due to the shortcomings of commercial filters and non-linear components for overvoltage protection in the conditions of synergy of neutron and gamma radiation and functional aging, the behavior of the hybrid protection circuit under the same conditions was examined. In order for the experimental procedure to correspond as closely as possible to the real situation, the load of the hybrid circuit was not adjusted by impedance. The standard model of the hybrid protection circuit recommended in accordance with IEC 1.3 is simulated using the software package PSPICE. To that end, it is necessary to create a varistor with appropriate elements. The equivalent inductance parameters were found to be stable in relation to the experimental conditions. It was also established that due to the synergy of neutron and gamma radiation and functional aging, there is a change in the steepness of the varistor characteristic and the tangent of the loss angle in the capacitors. The overall effect of neutron and gamma radiation and functional aging was tested on the hybrid circuit and on individual components. The experiments were performed under well-controlled laboratory conditions, and the combined measurement uncertainty of the experimental procedure did not exceed 5%.
{"title":"Influence of the synergy of neutron and gamma radiation and functional aging on the efficiency of a hybrid protection circuit","authors":"N. Kartalović, Alija Jusić, A. Zigic, Dušan P. Nikezić","doi":"10.2298/ntrp2203201k","DOIUrl":"https://doi.org/10.2298/ntrp2203201k","url":null,"abstract":"Due to the shortcomings of commercial filters and non-linear components for overvoltage protection in the conditions of synergy of neutron and gamma radiation and functional aging, the behavior of the hybrid protection circuit under the same conditions was examined. In order for the experimental procedure to correspond as closely as possible to the real situation, the load of the hybrid circuit was not adjusted by impedance. The standard model of the hybrid protection circuit recommended in accordance with IEC 1.3 is simulated using the software package PSPICE. To that end, it is necessary to create a varistor with appropriate elements. The equivalent inductance parameters were found to be stable in relation to the experimental conditions. It was also established that due to the synergy of neutron and gamma radiation and functional aging, there is a change in the steepness of the varistor characteristic and the tangent of the loss angle in the capacitors. The overall effect of neutron and gamma radiation and functional aging was tested on the hybrid circuit and on individual components. The experiments were performed under well-controlled laboratory conditions, and the combined measurement uncertainty of the experimental procedure did not exceed 5%.","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":"68549124","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}
V. Lukić, M. Spasojevic, Milentije Luković, M. Spasojević, A. Maricic
Kinetics and mechanism of hydrogen adsorption in as-obtained and ground nuclear graphite Wendelstein 7-X are examined. In the first time interval the adsorption process is determined by dissociation of the hydrogen molecule, occurring at the outer surface and in open micropores of nuclear graphite particles. However, in the second time interval, the slowest step in the hydrogen adsorption is inter-granular and inter-crystallite diffusion in nanopores of graphite. The X-ray analysis shows, that grinding of as-obtained nuclear graphite results in finer particles with finer nanocrystals and larger density of opened pores and carbon reactive sites. The capacity and rate of adsorption increase with comminution of nuclear graphite particles and adsorbed hydrogen does not substantially alter the microstructure of nuclear graphite.
{"title":"Hydrogen adsorption process in nanocrystalline nuclear graphite","authors":"V. Lukić, M. Spasojevic, Milentije Luković, M. Spasojević, A. Maricic","doi":"10.2298/ntrp2201011l","DOIUrl":"https://doi.org/10.2298/ntrp2201011l","url":null,"abstract":"Kinetics and mechanism of hydrogen adsorption in as-obtained and ground nuclear graphite Wendelstein 7-X are examined. In the first time interval the adsorption process is determined by dissociation of the hydrogen molecule, occurring at the outer surface and in open micropores of nuclear graphite particles. However, in the second time interval, the slowest step in the hydrogen adsorption is inter-granular and inter-crystallite diffusion in nanopores of graphite. The X-ray analysis shows, that grinding of as-obtained nuclear graphite results in finer particles with finer nanocrystals and larger density of opened pores and carbon reactive sites. The capacity and rate of adsorption increase with comminution of nuclear graphite particles and adsorbed hydrogen does not substantially alter the microstructure of nuclear graphite.","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":"68547453","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}
H. Tam, T. Sang, N. Anh, T. Trung, V. Quang, N. Dat, Lam Nhat, H. Chuong
The feasibility of an artificial neural network for the estimation of the liquid density, in gamma scattering measurement, has been investigated in this paper. The liquid density was estimated using a well-trained artificial neural network model with only two input parameters: the scattering angle and the ratio of the area under a single scattering peak for a liquid relative to that for water. It is worth noting that the whole training data was generated by carrying out the Monte Carlo simulation using Monte Carlo N-Particle code. The results indicated that the artificial neural network model exhibits a good correlation between the estimated and reference densities, at all the investigated scattering angles, with a relative error below 5.5 %. Next, the trained model is used to predict the liquid density with the input data of being the experimatal data, which yield the relative deviation between the predicted density and the reference one, mostly less than 5 % (only three cases with deviation in the range from 5-8.1 %). The obtained results demonstrated that the model developed in this work gives more accurate results within the defined conditions.
{"title":"Estimation of liquid density using artificial neural network in gamma-ray scattering measurement","authors":"H. Tam, T. Sang, N. Anh, T. Trung, V. Quang, N. Dat, Lam Nhat, H. Chuong","doi":"10.2298/ntrp2201031t","DOIUrl":"https://doi.org/10.2298/ntrp2201031t","url":null,"abstract":"The feasibility of an artificial neural network for the estimation of the liquid density, in gamma scattering measurement, has been investigated in this paper. The liquid density was estimated using a well-trained artificial neural network model with only two input parameters: the scattering angle and the ratio of the area under a single scattering peak for a liquid relative to that for water. It is worth noting that the whole training data was generated by carrying out the Monte Carlo simulation using Monte Carlo N-Particle code. The results indicated that the artificial neural network model exhibits a good correlation between the estimated and reference densities, at all the investigated scattering angles, with a relative error below 5.5 %. Next, the trained model is used to predict the liquid density with the input data of being the experimatal data, which yield the relative deviation between the predicted density and the reference one, mostly less than 5 % (only three cases with deviation in the range from 5-8.1 %). The obtained results demonstrated that the model developed in this work gives more accurate results within the defined conditions.","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":"68547618","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}
C. Ubeda, Dario Martinez, Luis Ramos, Juan Vega-Vargas, Teodoro Rivera, Marcus Oliveira, Dandaro Dalmazzo
The goal of this study was to generate the first values of local diagnostic reference levels for a range of fluoroscopically guided cardiac diagnostic and therapeutic procedures in adult patients in Chile and to compare radiation dose levels with others presented in the literature. The dosimetric data collection period was conducted over the whole of 2020. The local diagnostic reference levels were calculated as the 75th percentile of patient dose data distributions for kerma area-product values. The sample of collected clinical procedures (480) was divided into diagnostic and therapeutic procedures. The kerma area-product differences found between diagnostic and therapeutic procedures were statistically significant. The local diagnostic reference levels were 81.6 Gy cm2 and 166.9 Gycm2 for fluoroscopically guided cardiac diagnostic and therapeutic procedures, respectively. A comparison of our results with results found in the literature for the last 10 years, showed that there are no published papers for hospitals in Latin America and the Caribbean. It becomes urgent to be able to carry out more research of this type, given that the health reality between countries on different continents is very different. While in some the establishment of diagnostic reference levels is a legal obligation, in others it is a matter of good or bad will.
{"title":"First local diagnostic reference levels for fluoroscopically guided cardiac procedures in adult patients in Chile","authors":"C. Ubeda, Dario Martinez, Luis Ramos, Juan Vega-Vargas, Teodoro Rivera, Marcus Oliveira, Dandaro Dalmazzo","doi":"10.2298/ntrp2201084u","DOIUrl":"https://doi.org/10.2298/ntrp2201084u","url":null,"abstract":"The goal of this study was to generate the first values of local diagnostic reference levels for a range of fluoroscopically guided cardiac diagnostic and therapeutic procedures in adult patients in Chile and to compare radiation dose levels with others presented in the literature. The dosimetric data collection period was conducted over the whole of 2020. The local diagnostic reference levels were calculated as the 75th percentile of patient dose data distributions for kerma area-product values. The sample of collected clinical procedures (480) was divided into diagnostic and therapeutic procedures. The kerma area-product differences found between diagnostic and therapeutic procedures were statistically significant. The local diagnostic reference levels were 81.6 Gy cm2 and 166.9 Gycm2 for fluoroscopically guided cardiac diagnostic and therapeutic procedures, respectively. A comparison of our results with results found in the literature for the last 10 years, showed that there are no published papers for hospitals in Latin America and the Caribbean. It becomes urgent to be able to carry out more research of this type, given that the health reality between countries on different continents is very different. While in some the establishment of diagnostic reference levels is a legal obligation, in others it is a matter of good or bad will.","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":"68548193","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}
M. Živanović, Amra Šabeta, N. Kržanović, Vedrana Makaric, Milos Djaletic, Milica Stupar, S. Stankovic
This paper presents a comparison performed between two calibration laboratories in several radiation qualities, using dosimeters of varying quality as transfer instruments. The goal of this work was to investigate the viability of using field-class dosimeters for official comparisons and to determine if the calibration factors for field-class dosimeters are comparable between calibration laboratories within the stated measurement uncertainties. The results of the comparison were acceptable for high-quality electronic personal dosimeters in all radiation qualities, and such dosimeters could be used as transfer instruments. On the other hand, comparison results for low-quality dosimeters were often not acceptable, either due to pronounced energy dependence, low stability, or both. Such instruments are unreliable even under well-defined laboratory conditions, and their use in routine measurements may cause doubt in official data or influence public opinion. This problem is often hidden because many dosimeters are calibrated or verified only in 137Cs beams, where the deviations are the smallest. The largest differences are found for low-energy X-ray radiation qualities, where many dosimeters have significant overresponse.
{"title":"Comparison of calibration factors for field-class dosimeters","authors":"M. Živanović, Amra Šabeta, N. Kržanović, Vedrana Makaric, Milos Djaletic, Milica Stupar, S. Stankovic","doi":"10.2298/ntrp2202103z","DOIUrl":"https://doi.org/10.2298/ntrp2202103z","url":null,"abstract":"This paper presents a comparison performed between two calibration laboratories in several radiation qualities, using dosimeters of varying quality as transfer instruments. The goal of this work was to investigate the viability of using field-class dosimeters for official comparisons and to determine if the calibration factors for field-class dosimeters are comparable between calibration laboratories within the stated measurement uncertainties. The results of the comparison were acceptable for high-quality electronic personal dosimeters in all radiation qualities, and such dosimeters could be used as transfer instruments. On the other hand, comparison results for low-quality dosimeters were often not acceptable, either due to pronounced energy dependence, low stability, or both. Such instruments are unreliable even under well-defined laboratory conditions, and their use in routine measurements may cause doubt in official data or influence public opinion. This problem is often hidden because many dosimeters are calibrated or verified only in 137Cs beams, where the deviations are the smallest. The largest differences are found for low-energy X-ray radiation qualities, where many dosimeters have significant overresponse.","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":"68548383","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}
Special high-protein foods suitable for diabetics must be treated to ensure the complete absence of microorganisms and bacteria. It is also important to achieve that this treatment does not change the nutritional value of the product. Among the new decontamination technologies, low-energy electron-beam treatment has proven to be an effective technique for inactivating bacteria with minimal impact on food quality. The paper aims to analyze the influence of low-energy electron-beam irradiation on the microbiological properties and nutritional value of high-protein foods.
{"title":"Use of low-energy electron-beam in the treatment of special food products with a high protein content","authors":"Vuk Gajić, N. Mirković, Ivica Vujčić, S. Mašić","doi":"10.2298/ntrp2202153g","DOIUrl":"https://doi.org/10.2298/ntrp2202153g","url":null,"abstract":"Special high-protein foods suitable for diabetics must be treated to ensure the complete absence of microorganisms and bacteria. It is also important to achieve that this treatment does not change the nutritional value of the product. Among the new decontamination technologies, low-energy electron-beam treatment has proven to be an effective technique for inactivating bacteria with minimal impact on food quality. The paper aims to analyze the influence of low-energy electron-beam irradiation on the microbiological properties and nutritional value of high-protein foods.","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":"68548495","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 reduce the risk of leaking confidential information in nuclear arms control, we propose a new arms control inspection concept based on neutron activation analysis, in conjunction with physical shielding technology to distort the energy and propagation path of the outgoing particles in the physical domain. The reliability and security of this authentication concept are demonstrated using Monte Carlo simulations. It turns out that the concept can readily identify isotope cheats and two typical geometric cheats without revealing sensitive information about the inspected items.
{"title":"Nuclear disarmament verification based on (n,γ) reaction using physical encryption technology","authors":"Qing-Hua He, Xiao-Suo He, Tian Li, Kai-Kai Lu, Sheng-Kai Wang, Xiao-Min Dou, Xiao-Tao He","doi":"10.2298/ntrp2202167h","DOIUrl":"https://doi.org/10.2298/ntrp2202167h","url":null,"abstract":"To reduce the risk of leaking confidential information in nuclear arms control, we propose a new arms control inspection concept based on neutron activation analysis, in conjunction with physical shielding technology to distort the energy and propagation path of the outgoing particles in the physical domain. The reliability and security of this authentication concept are demonstrated using Monte Carlo simulations. It turns out that the concept can readily identify isotope cheats and two typical geometric cheats without revealing sensitive information about the inspected items.","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":"68548697","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}
In Nuclear Power Plants the Design Extension Conditions are more complex and severe than those postulated as Design Basis Accidents, therefore, they must be taken into account in the safety analyses. In this study, many hypothetical investigated transients are applied on KONVOI pressurized water reactor during a 6-in. (182 cm2) cold leg Small Break Loss-of-Coolant-Accident to revise the effects of all safety systems ways through their availability/ nonavailability on the thermal hydraulic behaviour of the reactor. The investigated transients are represented through three cases of Small Break Loss-of-Coolant-Accident as, case-1, without scram and all of the safety systems are failure, case-2, the normal scram actuation with failure of all safety systems (nonavailability), and finally case 3, with normal actuation scram sequence and normal sequential actuation of all safety systems (availability). These three investigated transient cases are simulated by creation a model using Analysis of Thermal-Hydraulics of LEaks and Transient code. In all transient cases, all types of reactivity feedbacks, boron, moderator density, moderator temperature and fuel temperature are considered. The steady-state results are nearly in agreement with the plant parameters available in previous literatures. The results show the importance effects of the feedbacks reactivity at Loss-of-Coolant-Accident on the fallouts power, since they are considered the key parameters for controlling the clad and fuel temperatures to maintain them below their melting point. Moreover, the calculated results in all cases show that the thermal hydraulic parameters are in acceptable ranges and encounter the safety criterion during Loss-of-Coolant-Accident the Design Extension Conditions accidents processes. Furthermore, the results show that the core uncovers and fuel heat up do not occur in KONVOI pressurized water reactor in theses the Design Extension Conditions simulations since, all safety systems provide adequate core cooling by sufficient water inventory into the core to cover it.
{"title":"Analysis of thermal hydraulic behavior of KONVOI PWR during a design extension condition","authors":"S. Helmy, M. Kandil, A. Refaey","doi":"10.2298/ntrp201209004h","DOIUrl":"https://doi.org/10.2298/ntrp201209004h","url":null,"abstract":"In Nuclear Power Plants the Design Extension Conditions are more complex and severe than those postulated as Design Basis Accidents, therefore, they must be taken into account in the safety analyses. In this study, many hypothetical investigated transients are applied on KONVOI pressurized water reactor during a 6-in. (182 cm2) cold leg Small Break Loss-of-Coolant-Accident to revise the effects of all safety systems ways through their availability/ nonavailability on the thermal hydraulic behaviour of the reactor. The investigated transients are represented through three cases of Small Break Loss-of-Coolant-Accident as, case-1, without scram and all of the safety systems are failure, case-2, the normal scram actuation with failure of all safety systems (nonavailability), and finally case 3, with normal actuation scram sequence and normal sequential actuation of all safety systems (availability). These three investigated transient cases are simulated by creation a model using Analysis of Thermal-Hydraulics of LEaks and Transient code. In all transient cases, all types of reactivity feedbacks, boron, moderator density, moderator temperature and fuel temperature are considered. The steady-state results are nearly in agreement with the plant parameters available in previous literatures. The results show the importance effects of the feedbacks reactivity at Loss-of-Coolant-Accident on the fallouts power, since they are considered the key parameters for controlling the clad and fuel temperatures to maintain them below their melting point. Moreover, the calculated results in all cases show that the thermal hydraulic parameters are in acceptable ranges and encounter the safety criterion during Loss-of-Coolant-Accident the Design Extension Conditions accidents processes. Furthermore, the results show that the core uncovers and fuel heat up do not occur in KONVOI pressurized water reactor in theses the Design Extension Conditions simulations since, all safety systems provide adequate core cooling by sufficient water inventory into the core to cover it.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68545604","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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