This paper describes a digital reactivity meter module based on solving the inverse kinetics equations and the time behavior of the output pulse frequency from the amplifier, which is proportional to the power of the Dalat Nuclear Research Reactor (DNRR). The designed reactivity meter, which operates online with real-time calculation, was tested using the PGT-17R simulator signals in comparison with the existing imported module PNO-121R5 of the DNRR’s control and protection system. The experimental results show that the technical characteristics and functions of the two modules are equivalent.
{"title":"Design of a FPGA-based digital reactivity meter for Dalat Nuclear Research Reactor","authors":"V. Vo, V. Nguyen, Nhi-Dien Nguyen, Van Hiep Le","doi":"10.53747/nst.v11i4.350","DOIUrl":"https://doi.org/10.53747/nst.v11i4.350","url":null,"abstract":"This paper describes a digital reactivity meter module based on solving the inverse kinetics equations and the time behavior of the output pulse frequency from the amplifier, which is proportional to the power of the Dalat Nuclear Research Reactor (DNRR). The designed reactivity meter, which operates online with real-time calculation, was tested using the PGT-17R simulator signals in comparison with the existing imported module PNO-121R5 of the DNRR’s control and protection system. The experimental results show that the technical characteristics and functions of the two modules are equivalent.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"12 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87078047","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
T. Pham, T. Nguyen, Nhut Khanh Chu, V. Cao, Binh Doan, Ngoc Thao Nguyen Nguyen, T. Nguyen
1% carrageenan oligosaccharide solutions obtained by electron beam irradiation at the radiation doses of 9 kGy (CO-9) and 30 kGy (CO-30) were applied for shrimps before frozen, and their effects on quality of frozen shrimps were investigated by observing the microstructure of shrimp’s muscle tissue, measuring their weight loss (%), hardness and pH after thawing. Comparison with the shrimps treated by 1% tetrasodium pyrophosphate solution (Na4P2O7, positive control) and distilled water (negative control), the shrimp samples soaked in CO before frozen kept their initial properties, and the shrimps treated by CO-30 solution showed better quality than others after 3 weeks of frozen storage. Specifically, the mean distances of muscle bundles and muscle fibers in the shrimps soaked in CO-30 solution were 23.9 µm and 11.1 µm, respectively, much smaller than 37.9 µm and 14.8 µm in the shrimps treated by Na4P2O7, and 46.7 µm and 19.8 µm in the shrimps soaked in distilled water only. Our results also revealed that the weight loss after thawing and pH of the shrimps soaked in CO-30 solution were 1.55% and 6.40, much lower than that of the positive control sample (2.59% and 6.82) and negative control sample (4.83% and 6.58), respectively. In contrast, the mean of hardness of the sample soaked in CO-30 solution was 20.4, about 20.7 and 36.0% higher than those of positive control (16.9) and negative control (15.0). These results suggested that CO-30 is effective to inhibit the denaturation of shrimp during frozen storage and can be applied to prolong the shelf life and keep the quality of frozen shrimp products.
{"title":"Effects of carrageenan oligosaccharides prepared by electron beam irradiation on frozen shrimps during storage","authors":"T. Pham, T. Nguyen, Nhut Khanh Chu, V. Cao, Binh Doan, Ngoc Thao Nguyen Nguyen, T. Nguyen","doi":"10.53747/nst.v11i4.331","DOIUrl":"https://doi.org/10.53747/nst.v11i4.331","url":null,"abstract":"1% carrageenan oligosaccharide solutions obtained by electron beam irradiation at the radiation doses of 9 kGy (CO-9) and 30 kGy (CO-30) were applied for shrimps before frozen, and their effects on quality of frozen shrimps were investigated by observing the microstructure of shrimp’s muscle tissue, measuring their weight loss (%), hardness and pH after thawing. Comparison with the shrimps treated by 1% tetrasodium pyrophosphate solution (Na4P2O7, positive control) and distilled water (negative control), the shrimp samples soaked in CO before frozen kept their initial properties, and the shrimps treated by CO-30 solution showed better quality than others after 3 weeks of frozen storage. Specifically, the mean distances of muscle bundles and muscle fibers in the shrimps soaked in CO-30 solution were 23.9 µm and 11.1 µm, respectively, much smaller than 37.9 µm and 14.8 µm in the shrimps treated by Na4P2O7, and 46.7 µm and 19.8 µm in the shrimps soaked in distilled water only. Our results also revealed that the weight loss after thawing and pH of the shrimps soaked in CO-30 solution were 1.55% and 6.40, much lower than that of the positive control sample (2.59% and 6.82) and negative control sample (4.83% and 6.58), respectively. In contrast, the mean of hardness of the sample soaked in CO-30 solution was 20.4, about 20.7 and 36.0% higher than those of positive control (16.9) and negative control (15.0). These results suggested that CO-30 is effective to inhibit the denaturation of shrimp during frozen storage and can be applied to prolong the shelf life and keep the quality of frozen shrimp products.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"285 ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91454646","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Tuyen Luu Anh, Hung Nguyen, N. Tiep, D. Phuc, P. Phuc, L. Thai, T. Xuan, P. Huế, N. Hue, L. Nguyen, N. Trung
Due to the rapid scientific and technological development in the last decades, basic research in solid state physics, chemistry and material science has focused on objects and phenomena more and more confined in dimensions and time-scale, and well visible for the general publicity by introducing the terms “nanophysics, nanoscience, nanomaterials, etc.”, often featured in the media. Researchers therefore keep searching for better and better investigative techniques. Various nuclear analytical spectroscopies, such as Positron annihilation lifetime (PAL), Doppler broadening of positron annihilation energy (DB), Electron momentum distribution (EMD), Slow positron beam (SPB), Neutron diffractions (ND), Rutherford backscattering (RBS), etc., have proved themselves as useful tools for microscopic analysis of different material’s structure ranging from angstrom (Ȧ) to nanometer (nm) scales. Besides, ion beams generated from accelerators (electron, 1H, 2He, 40Ar, 86Kr, 109Ag, 123Xe, 184W, etc.) have also become very effective tools for modifying the micro structure of nanomaterials. These methods have been intensively utilized by our group at Vinatom with external collaborations from JINR (Dubna) in order to study the in-depth structure of different nanomaterials. This report introduces our research and collaborative activities, facilities and some recent highlighted results.
{"title":"Application of nuclear analytical spectroscopies and ion beams to the study of nanomaterials: cooperative projects between Vinatom and JINR (Dubna)","authors":"Tuyen Luu Anh, Hung Nguyen, N. Tiep, D. Phuc, P. Phuc, L. Thai, T. Xuan, P. Huế, N. Hue, L. Nguyen, N. Trung","doi":"10.53747/nst.v12i1.349","DOIUrl":"https://doi.org/10.53747/nst.v12i1.349","url":null,"abstract":"Due to the rapid scientific and technological development in the last decades, basic research in solid state physics, chemistry and material science has focused on objects and phenomena more and more confined in dimensions and time-scale, and well visible for the general publicity by introducing the terms “nanophysics, nanoscience, nanomaterials, etc.”, often featured in the media. Researchers therefore keep searching for better and better investigative techniques. Various nuclear analytical spectroscopies, such as Positron annihilation lifetime (PAL), Doppler broadening of positron annihilation energy (DB), Electron momentum distribution (EMD), Slow positron beam (SPB), Neutron diffractions (ND), Rutherford backscattering (RBS), etc., have proved themselves as useful tools for microscopic analysis of different material’s structure ranging from angstrom (Ȧ) to nanometer (nm) scales. Besides, ion beams generated from accelerators (electron, 1H, 2He, 40Ar, 86Kr, 109Ag, 123Xe, 184W, etc.) have also become very effective tools for modifying the micro structure of nanomaterials. These methods have been intensively utilized by our group at Vinatom with external collaborations from JINR (Dubna) in order to study the in-depth structure of different nanomaterials. This report introduces our research and collaborative activities, facilities and some recent highlighted results.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"25 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90564596","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Huu Loi Le, Hoang Long Nguyen, Quang Son Ong, M. Ho, Van Hoang Dao, Truong Son Truong, Van Tien Vo, Quang Vuong Le
Narrow spectrum series from N-40 to N-120 were established according to ISO 4037:2019. This study was made through experimental measurements and the software modeling toolkit SpekPy v2.0. Experiments were performed to determine Inherent filtration (0.332 & 0.492 mm Al at 100 cm & 250 cm, respectively). The maximum deviation compared to ISO 4037:2019 of the measured HVLs values are not more then 0.10 mm Al and for modeling not exceed 0.09 mm Al; h range 0.91 to 0.97 for experimently and 0.89 to 0.96 for modeling (0.88 - 1, ISO 4037-1:2019). The maximum contribution of scattering is value 4.0% (< 5%, ISO 4037-1:2019). Radiation field uniformity of N-40 to N-120 should list all categories in detail 12.5, 11.0, 10.0, 9.0, 8.5 cm at 100 cm distance; and 35.5, 31.5, 29.0, 26.5, 24.5 cm at 250 cm beam center axis distance. On the basis of ISO 4037:2019, air kerma values at 100 cm and 250 cm have also been determined with uncertainties 3.85% to 5.18% for experimently and 3.41% to 4.19% for modeling (not exceed 10%, ISO 4037:2019). Therefore, the X-ray radiation field has been well established in compliance with the ISO 4037:2019, it can be used for calibrating survey meters and personal dosimeters.
根据ISO 4037:2019建立从N-40到N-120的窄光谱系列。本研究通过实验测量和软件建模工具包SpekPy v2.0进行。实验测定固有滤过率(在100 cm和250 cm处分别为0.332和0.492 mm Al)。与ISO 4037:2019测量的HVLs值相比，最大偏差不超过0.10 mm Al，建模不超过0.09 mm Al;h范围0.91至0.97的实验和0.89至0.96的建模(0.88 -1,ISO 4037-1:2019)。散射的最大贡献值为4.0% (< 5%，ISO 4037-1:2019)。N-40 ~ N-120的辐射场均匀性应详细列出在100 cm距离处12.5、11.0、10.0、9.0、8.5 cm的所有类别;和35.5、31.5、29.0、26.5、24.5 cm处250 cm梁中心轴线距离。在ISO 4037:2019的基础上，还确定了100 cm和250 cm处的空气kerma值，实验不确定度为3.85%至5.18%，建模不确定度为3.41%至4.19%(不超过10%，ISO 4037:2019)。因此，x射线辐射领域已根据ISO 4037:2019建立，可用于校准调查仪表和个人剂量计。
{"title":"Establishment and quality assessment of X-ray narrow spectrum series according to ISO 4037:2019 at SSDL of center for nuclear technologies","authors":"Huu Loi Le, Hoang Long Nguyen, Quang Son Ong, M. Ho, Van Hoang Dao, Truong Son Truong, Van Tien Vo, Quang Vuong Le","doi":"10.53747/nst.v12i1.374","DOIUrl":"https://doi.org/10.53747/nst.v12i1.374","url":null,"abstract":"Narrow spectrum series from N-40 to N-120 were established according to ISO 4037:2019. This study was made through experimental measurements and the software modeling toolkit SpekPy v2.0. Experiments were performed to determine Inherent filtration (0.332 & 0.492 mm Al at 100 cm & 250 cm, respectively). The maximum deviation compared to ISO 4037:2019 of the measured HVLs values are not more then 0.10 mm Al and for modeling not exceed 0.09 mm Al; h range 0.91 to 0.97 for experimently and 0.89 to 0.96 for modeling (0.88 - 1, ISO 4037-1:2019). The maximum contribution of scattering is value 4.0% (< 5%, ISO 4037-1:2019). Radiation field uniformity of N-40 to N-120 should list all categories in detail 12.5, 11.0, 10.0, 9.0, 8.5 cm at 100 cm distance; and 35.5, 31.5, 29.0, 26.5, 24.5 cm at 250 cm beam center axis distance. On the basis of ISO 4037:2019, air kerma values at 100 cm and 250 cm have also been determined with uncertainties 3.85% to 5.18% for experimently and 3.41% to 4.19% for modeling (not exceed 10%, ISO 4037:2019). Therefore, the X-ray radiation field has been well established in compliance with the ISO 4037:2019, it can be used for calibrating survey meters and personal dosimeters.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"51 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86427798","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Isomeric ratios of isomeric pairs produced by photonuclear reactions (γ, n) on Se, Ce, Eu and Hg targets induced by bremsstrahlung with endpoint energies in the giant dipole resonance region have been theoretically calculated using TALYS 1.95 code in combination with Geant4 simulation. The computed isomeric ratios as a function of the bremsstrahlung endpoint energies in the range of 10 to 25 MeV resulted from convolution between calculated differential cross-sections using six level density models available in TALYS 1.95 and the bremsstrahlung spectra simulated by the GEANT4 toolkit. Moreover, for each level density model, eight gamma strength functions have been employed. The calculated results are compared to the experimental data in the existing literature for Talys 1.95 model evaluation.
{"title":"Theoretical consideration of isomeric ratios in some photonuclear reactions induced by bremsstrahlung with endpoint energy in giant dipole resonance region using Talys 1.95 code","authors":"Minh Hue Bui, D. T. Tran","doi":"10.53747/nst.v12i1.373","DOIUrl":"https://doi.org/10.53747/nst.v12i1.373","url":null,"abstract":"Isomeric ratios of isomeric pairs produced by photonuclear reactions (γ, n) on Se, Ce, Eu and Hg targets induced by bremsstrahlung with endpoint energies in the giant dipole resonance region have been theoretically calculated using TALYS 1.95 code in combination with Geant4 simulation. The computed isomeric ratios as a function of the bremsstrahlung endpoint energies in the range of 10 to 25 MeV resulted from convolution between calculated differential cross-sections using six level density models available in TALYS 1.95 and the bremsstrahlung spectra simulated by the GEANT4 toolkit. Moreover, for each level density model, eight gamma strength functions have been employed. The calculated results are compared to the experimental data in the existing literature for Talys 1.95 model evaluation.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"85 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91330828","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
D. Duong, Tuan Nam Pham, Dac Dung Bui, Thi Oanh Nguyen, T. H. Doan, Van Khanh Nguyen, Huyen-Trang Nguyen, Hoang Giang Nguyen
In this study, ARGOS software was used to simulate the atmospheric radioactive emissions from Fangchenggang nuclear power plant to Viet Nam. The simulated cases are hypothetical accidents with hypothetical source terms equivalent to level 6 of the International Nuclear and radiological Event Scale (INES). The results show the possibility of using ARGOS in simulating atmospheric dispersion, assessing radiation dose to humans from the Fangchenggang nuclear power plant accident to Viet Nam in some accident situations. Furthermore, the obtained results contribute to forecasting and supporting emergency response when an accident occurs in nuclear power plants.
{"title":"Using ARGOS to simulate radioactive dispersion in the atmosphere from Fangchenggang nuclear power plant to Viet Nam","authors":"D. Duong, Tuan Nam Pham, Dac Dung Bui, Thi Oanh Nguyen, T. H. Doan, Van Khanh Nguyen, Huyen-Trang Nguyen, Hoang Giang Nguyen","doi":"10.53747/nst.v11i4.329","DOIUrl":"https://doi.org/10.53747/nst.v11i4.329","url":null,"abstract":"In this study, ARGOS software was used to simulate the atmospheric radioactive emissions from Fangchenggang nuclear power plant to Viet Nam. The simulated cases are hypothetical accidents with hypothetical source terms equivalent to level 6 of the International Nuclear and radiological Event Scale (INES). The results show the possibility of using ARGOS in simulating atmospheric dispersion, assessing radiation dose to humans from the Fangchenggang nuclear power plant accident to Viet Nam in some accident situations. Furthermore, the obtained results contribute to forecasting and supporting emergency response when an accident occurs in nuclear power plants.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"25 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88056439","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Dac Dung Bui, D. Duong, V. Duong, Thu Bac Vuong, Thi Ha Thanh Nguyen, T. H. Doan, Thi Oanh Nguyen, Dinh Cuong Le, Hoang Giang Nguyen, Huyen-Trang Nguyen
Sediment cores were taken in the coastal area of Ba Lat estuary (Red River), in the Xuan Thuy national park. Each core was cut into slices of 4 cm in thickness, numbered from top to bottom and then analyzing for radionuclides (226Ra, 137Cs and 210Pb). Computational dating models were used to determine the age and sedimentation rate for each sediment core. This report presents the results of applying computational models to the sediment core BL13 that could provide a general methodology for determining the age and the sedimentation rate of the sediment cores taken in the coastal area of Ba Lat estuary. Results show that Constant rate of supply (CRS) model is probably the best model for determining the sedimentation rate. For the sediment core BL13, the use of the Composite model by adjusting the results of the CRS model in combination with the time marker of August 1971 (the time of the historical flood event on the Red River) seems to give the most reasonable results. The average sedimentation rate at the BL13 site before 1960 was about 0.5 cm/year. The rate had increased significantly from 1960, up to the highest value of 1.5 cm year-1 in the 1970s and then decreased to about 1.0 to 1.2 cm/year from the 1980s to the present. The change in the sedimentation rate could be caused by the main flow changes and large floods of the Red River from 1960 to 1980.
{"title":"Use of 210Pb dating models for estimating sedimentation rate of a typical sediment core taken in the Ba Lat coastal area (Red River)","authors":"Dac Dung Bui, D. Duong, V. Duong, Thu Bac Vuong, Thi Ha Thanh Nguyen, T. H. Doan, Thi Oanh Nguyen, Dinh Cuong Le, Hoang Giang Nguyen, Huyen-Trang Nguyen","doi":"10.53747/nst.v12i1.348","DOIUrl":"https://doi.org/10.53747/nst.v12i1.348","url":null,"abstract":"Sediment cores were taken in the coastal area of Ba Lat estuary (Red River), in the Xuan Thuy national park. Each core was cut into slices of 4 cm in thickness, numbered from top to bottom and then analyzing for radionuclides (226Ra, 137Cs and 210Pb). Computational dating models were used to determine the age and sedimentation rate for each sediment core. This report presents the results of applying computational models to the sediment core BL13 that could provide a general methodology for determining the age and the sedimentation rate of the sediment cores taken in the coastal area of Ba Lat estuary. Results show that Constant rate of supply (CRS) model is probably the best model for determining the sedimentation rate. For the sediment core BL13, the use of the Composite model by adjusting the results of the CRS model in combination with the time marker of August 1971 (the time of the historical flood event on the Red River) seems to give the most reasonable results. The average sedimentation rate at the BL13 site before 1960 was about 0.5 cm/year. The rate had increased significantly from 1960, up to the highest value of 1.5 cm year-1 in the 1970s and then decreased to about 1.0 to 1.2 cm/year from the 1980s to the present. The change in the sedimentation rate could be caused by the main flow changes and large floods of the Red River from 1960 to 1980.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"51 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88995492","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Thi Hong Ngoc Le, Ngoc Dat Nguyen, Van Thai Nguyen
The most widely studied LOCA (Loss of Coolant Accidents) is a rupture of a cold leg pipe causing the Reactor Cooling System to depressurize first, with different break sizes corresponding to the change in trigger signal from the Instrument and Control System (I&C System) such as pressure, temperature, power, pressure vessel water level, etc. is different. Therefore, the response of nuclear power plant varies considerably with the size of break. To mitigate the consequence of LOCA with a given break size, it is necessary to design the emergency core coolant systems so that the fuel is cooled efficiently during all phases of the accident. Therefore, the size of rupture needs to be detected and identified as soon as possible right after reactor scram. To achieve this goal, this study is conducted to investigate the applicability of artificial neural networks (ANN) for recognizing LOCAs, especially identifying the rupture sizes of the LOCAs according to the changes of operational parameters of VVER-1000 nuclear power plant. This study mainly focuses on building, training, and optimizing the artificial neural networks using simulation databases obtained from the RELAP5 simulation program for VVER-1000 reactor technology. Results clearly showed the potential application of ANN-based model for detecting the break size even with uncertainty of input parameters added.
{"title":"Identification of Cold-Leg Break Size in LOCA Accident using Artificial Neural Networks and Simulation Database","authors":"Thi Hong Ngoc Le, Ngoc Dat Nguyen, Van Thai Nguyen","doi":"10.53747/nst.v11i4.339","DOIUrl":"https://doi.org/10.53747/nst.v11i4.339","url":null,"abstract":"The most widely studied LOCA (Loss of Coolant Accidents) is a rupture of a cold leg pipe causing the Reactor Cooling System to depressurize first, with different break sizes corresponding to the change in trigger signal from the Instrument and Control System (I&C System) such as pressure, temperature, power, pressure vessel water level, etc. is different. Therefore, the response of nuclear power plant varies considerably with the size of break. To mitigate the consequence of LOCA with a given break size, it is necessary to design the emergency core coolant systems so that the fuel is cooled efficiently during all phases of the accident. Therefore, the size of rupture needs to be detected and identified as soon as possible right after reactor scram. To achieve this goal, this study is conducted to investigate the applicability of artificial neural networks (ANN) for recognizing LOCAs, especially identifying the rupture sizes of the LOCAs according to the changes of operational parameters of VVER-1000 nuclear power plant. This study mainly focuses on building, training, and optimizing the artificial neural networks using simulation databases obtained from the RELAP5 simulation program for VVER-1000 reactor technology. Results clearly showed the potential application of ANN-based model for detecting the break size even with uncertainty of input parameters added.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"70 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82795435","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-01-01DOI: 10.12677/nst.2023.113029
娟 王
{"title":"Feasibility Study and Analysis of Intelligent Technology Application in Nuclear Power Industry","authors":"娟 王","doi":"10.12677/nst.2023.113029","DOIUrl":"https://doi.org/10.12677/nst.2023.113029","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"30 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77006939","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-01-01DOI: 10.12677/nst.2023.113033
鹏鹤 张
{"title":"Applied Research on Quality Function Deployment in PWR Fuel Rod Design and Manufacturing","authors":"鹏鹤 张","doi":"10.12677/nst.2023.113033","DOIUrl":"https://doi.org/10.12677/nst.2023.113033","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":"64 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81384848","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：