Pub Date : 2020-12-21DOI: 10.1504/ijnest.2020.10034468
Malik S. Mehemed, S. Obaid, F. A. Majeed
This study focuses on using a semi-classical and quantum mechanical approach based originally on the theory of Winther and Alder that is used to explain the Coulomb excitation. This approach is called the coupled channels with continuum-discretised (CCCD), where the semi-classical and quantum models were used to investigate the channel coupling effects on the determination of the cross section for fusion σfus (mb) and the distribution of the fusion barrier Dfus (mb/MeV) for systems 14N+59Co, 16O+64Ni and 18O+64Ni. The comparison between the results of the semi-classical and quantum mechanical models along with the corresponding experimental data shows clearly that the adopted semi-classical model is very competitive to the quantum mechanical model and can be considered as efficient approach to study the properties of the fusion reactions.
{"title":"Coupled channels calculation of fusion reaction for selected medium systems","authors":"Malik S. Mehemed, S. Obaid, F. A. Majeed","doi":"10.1504/ijnest.2020.10034468","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034468","url":null,"abstract":"This study focuses on using a semi-classical and quantum mechanical approach based originally on the theory of Winther and Alder that is used to explain the Coulomb excitation. This approach is called the coupled channels with continuum-discretised (CCCD), where the semi-classical and quantum models were used to investigate the channel coupling effects on the determination of the cross section for fusion σfus (mb) and the distribution of the fusion barrier Dfus (mb/MeV) for systems 14N+59Co, 16O+64Ni and 18O+64Ni. The comparison between the results of the semi-classical and quantum mechanical models along with the corresponding experimental data shows clearly that the adopted semi-classical model is very competitive to the quantum mechanical model and can be considered as efficient approach to study the properties of the fusion reactions.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"165"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42427719","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 : 2020-12-21DOI: 10.1504/ijnest.2020.10034466
M. Zubair, Samar S. Ahmed, Ahmad A. Ababneh, Abdullah Omar, Abdel-rahman Mohamed
Radiation monitoring deals with the sampling and measurement of different products found in different radiation pathways from the environment ending with consumption in humans. The aim of this research is to measure the radioactivity in the food products from different cities in the United Arab Emirates. Gamma-spectroscopy is the main tool for measurement that is adopted in this research, available in University of Sharjah and the Sharjah Municipality laboratories. The samples of milk, honey and dates were analysed to measure the radiation level. Milk and date samples were counted for 18 hours, and the measurement time for honey was around 48 hours. The count rate of 40K, 131I, 134Cs and 137Cs was measured for different types of milk, dates and honey produced in the UAE. The count rate of 131I, 134Cs and 137Cs was undetected in all samples. However, a 40K peak was present in all spectra and found to be 0.0149 [cps], 0.0294 [cps] and 0.0189 [cps] in the milk, dates and honey samples respectively. The results acquired from the tests were compared with similar studies in the past and were found to be of high similarity. The findings of this research reveal the absence of radionuclides in the food products.
{"title":"Gamma spectroscopy for the investigation of radiation contamination in the UAE","authors":"M. Zubair, Samar S. Ahmed, Ahmad A. Ababneh, Abdullah Omar, Abdel-rahman Mohamed","doi":"10.1504/ijnest.2020.10034466","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10034466","url":null,"abstract":"Radiation monitoring deals with the sampling and measurement of different products found in different radiation pathways from the environment ending with consumption in humans. The aim of this research is to measure the radioactivity in the food products from different cities in the United Arab Emirates. Gamma-spectroscopy is the main tool for measurement that is adopted in this research, available in University of Sharjah and the Sharjah Municipality laboratories. The samples of milk, honey and dates were analysed to measure the radiation level. Milk and date samples were counted for 18 hours, and the measurement time for honey was around 48 hours. The count rate of 40K, 131I, 134Cs and 137Cs was measured for different types of milk, dates and honey produced in the UAE. The count rate of 131I, 134Cs and 137Cs was undetected in all samples. However, a 40K peak was present in all spectra and found to be 0.0149 [cps], 0.0294 [cps] and 0.0189 [cps] in the milk, dates and honey samples respectively. The results acquired from the tests were compared with similar studies in the past and were found to be of high similarity. The findings of this research reveal the absence of radionuclides in the food products.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"14 1","pages":"141"},"PeriodicalIF":0.0,"publicationDate":"2020-12-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42059442","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030868
Malik H. Kheder, L. A. Najam, R. Mahmood, F. A. Majeed
Wheat and barley crops are used as food by humans and animals, their health effects on human life must be under the control, so it is important to measure their radiation concentrations. This work aimed to determine radon, radium, and uranium in barley and wheat crops planted in the Nineveh plains region. The technique of alpha track registration by CR-39 detector is used in measurements of the samples from ten planted locations. Radon, radium, and uranium mean concentrations found are 92.58 Bq.m−3, 0.4212 Bq kg−1 and 0.368 ppm, respectively. The uranium activity concentration and the total annual effective dose equivalent mean values are 4.546 Bq.kg−1 and 67.73 μSv/y. The results showed that the activity in locations depends on the agriculture soil of the area, and the amount of fertiliser applied in soil. All results are below the world permissible limits so the wheat and barley in the studied area are safe for consumption.
{"title":"Radioactivity concentrations in barley and wheat crops in Nineveh plain region in Iraq","authors":"Malik H. Kheder, L. A. Najam, R. Mahmood, F. A. Majeed","doi":"10.1504/ijnest.2020.10030868","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030868","url":null,"abstract":"Wheat and barley crops are used as food by humans and animals, their health effects on human life must be under the control, so it is important to measure their radiation concentrations. This work aimed to determine radon, radium, and uranium in barley and wheat crops planted in the Nineveh plains region. The technique of alpha track registration by CR-39 detector is used in measurements of the samples from ten planted locations. Radon, radium, and uranium mean concentrations found are 92.58 Bq.m−3, 0.4212 Bq kg−1 and 0.368 ppm, respectively. The uranium activity concentration and the total annual effective dose equivalent mean values are 4.546 Bq.kg−1 and 67.73 μSv/y. The results showed that the activity in locations depends on the agriculture soil of the area, and the amount of fertiliser applied in soil. All results are below the world permissible limits so the wheat and barley in the studied area are safe for consumption.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49410402","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030863
D. Hartanto, Safa Alhamad, K. Mahmoud, N. Kurdi, M. Zubair
A design of an advanced small modular reactor with long-life core is being studied in this paper. The core is designed to produce 45 MWth power with a lifetime of 20 years without refuelling. In order to achieve a compact design and have a good neutron economy, lead is considered as the coolant due to its excellent neutronics and thermo-physical properties. However, the lead coolant speed in the core is limited to 2 m/s to minimise the corrosion and erosion of the structural materials. On the other hand, U15N is used as the fuel which reflects excellent thermophysical properties and compatibility with lead. In this study, the neutronics properties of the core including the reactivity evolution during its lifetime, the control rod worth, and the fuel and coolant reactivity feedbacks are evaluated. It was found that ALMANAR could achieve a long-life core of about 22 effective full power years with very excellent inherent safety features. Monte Carlo Serpent code is used to perform the calculations in conjunction with the latest nuclear data library ENDF/B-VIII.0.
{"title":"Neutronics design study of an advanced lead-cooled modular nuclear reactor (ALMANAR)","authors":"D. Hartanto, Safa Alhamad, K. Mahmoud, N. Kurdi, M. Zubair","doi":"10.1504/ijnest.2020.10030863","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030863","url":null,"abstract":"A design of an advanced small modular reactor with long-life core is being studied in this paper. The core is designed to produce 45 MWth power with a lifetime of 20 years without refuelling. In order to achieve a compact design and have a good neutron economy, lead is considered as the coolant due to its excellent neutronics and thermo-physical properties. However, the lead coolant speed in the core is limited to 2 m/s to minimise the corrosion and erosion of the structural materials. On the other hand, U15N is used as the fuel which reflects excellent thermophysical properties and compatibility with lead. In this study, the neutronics properties of the core including the reactivity evolution during its lifetime, the control rod worth, and the fuel and coolant reactivity feedbacks are evaluated. It was found that ALMANAR could achieve a long-life core of about 22 effective full power years with very excellent inherent safety features. Monte Carlo Serpent code is used to perform the calculations in conjunction with the latest nuclear data library ENDF/B-VIII.0.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43896740","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030865
P. Divya, C. Kaliprasad, V. Prakash
The concentrations of natural radionuclides 40K, 226Ra and 232Th in sand samples collected from southern coastal parts of Kerala were determined by NaI(Tl) detector. The activities obtained for various grain sizes have been compared in order to understand the enrichment pattern. Sand with a grain size of 63-125 μm showed enhanced level of radionuclides concentration. The dose to the populace was also calculated from the activities of radionuclides in order to assess the radiation hazards. The calculated values of risk assessment parameters were not within the safe limits, which indicates the radiation hazards to the population due to these radionuclides are significant. However, the observed dose rates were well below the reported average values for other high background radiation areas. The results of the present systematic investigation are presented and discussed here in detail.
{"title":"A systematic investigation on grain size enrichment of radionuclides and assessment of radiation hazards along the southern coastal environment of Kerala, India","authors":"P. Divya, C. Kaliprasad, V. Prakash","doi":"10.1504/ijnest.2020.10030865","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030865","url":null,"abstract":"The concentrations of natural radionuclides 40K, 226Ra and 232Th in sand samples collected from southern coastal parts of Kerala were determined by NaI(Tl) detector. The activities obtained for various grain sizes have been compared in order to understand the enrichment pattern. Sand with a grain size of 63-125 μm showed enhanced level of radionuclides concentration. The dose to the populace was also calculated from the activities of radionuclides in order to assess the radiation hazards. The calculated values of risk assessment parameters were not within the safe limits, which indicates the radiation hazards to the population due to these radionuclides are significant. However, the observed dose rates were well below the reported average values for other high background radiation areas. The results of the present systematic investigation are presented and discussed here in detail.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48219892","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030864
Noor Adil Mohammed, S. A. Ebrahiem
Gamma radiation emitted by the radionuclides that exist in the soil is the biggest contributor to ionising radiation exposure which has enough energy to ionise or excited the atoms of the substance. Eighteen topsoil samples were taken from some locations in Baghdad to analyse and determine the specific activity of the radionuclides (238U, 232Th, 40K, and 137Cs) using gamma spectroscopy systems with an HPGe at the efficiency of 40%. The mean value results of the specific activity for 238U, 232Th, 40K, and 137Cs are 15.692±1.755 Bq/kg, 22.560±3.22 Bq/kg, 386.053±21.58 Bq/kg, and 12.0773±1.23 Bq/kg, respectively. The mean value results of indicators gamma (Raeq, Dy, DCs, AEDEin, AEDEout, Hex, Hin, and Iγ) are 74.383 Bq/kg, 36.320 nGy/h, 2.042 nGy/h, 0.178 mSv/y, 0.045 mSv/y, 0.248, 0.206, and 0.577. The mean values of specific activities and indicators of gamma hazard are within the acceptable limit given by UNSEAR, so, there is no hazard to humans lives in areas under study.
{"title":"Radioactivity levels of 238U, 234Th, 40K and 137C in the soil surface of selected regions from Baghdad governorate","authors":"Noor Adil Mohammed, S. A. Ebrahiem","doi":"10.1504/ijnest.2020.10030864","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030864","url":null,"abstract":"Gamma radiation emitted by the radionuclides that exist in the soil is the biggest contributor to ionising radiation exposure which has enough energy to ionise or excited the atoms of the substance. Eighteen topsoil samples were taken from some locations in Baghdad to analyse and determine the specific activity of the radionuclides (238U, 232Th, 40K, and 137Cs) using gamma spectroscopy systems with an HPGe at the efficiency of 40%. The mean value results of the specific activity for 238U, 232Th, 40K, and 137Cs are 15.692±1.755 Bq/kg, 22.560±3.22 Bq/kg, 386.053±21.58 Bq/kg, and 12.0773±1.23 Bq/kg, respectively. The mean value results of indicators gamma (Raeq, Dy, DCs, AEDEin, AEDEout, Hex, Hin, and Iγ) are 74.383 Bq/kg, 36.320 nGy/h, 2.042 nGy/h, 0.178 mSv/y, 0.045 mSv/y, 0.248, 0.206, and 0.577. The mean values of specific activities and indicators of gamma hazard are within the acceptable limit given by UNSEAR, so, there is no hazard to humans lives in areas under study.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43849810","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030870
Md. Ajijul Hoq, Md. Abdul Malek Soner, M. Salam, Mizanur Rahman, N. Jahan
The present study focused on the monthly or annual 41Ar activity release rate and ground level activity concentration measurement including the estimation of public dose level at the ground and stack positions of the Bangladesh Atomic Energy Commission TRIGA Research. During the experimental work, a Geiger-Muller (G-M) counter was used for the air sample count rate study. The experimental results demonstrated that the obtained maximum monthly or annual 41Ar activity release rate (2.48 × 1010 Bq/month or 6.25 × 1011 Bq/year) and monthly maximum ground level 41Ar activity concentration (6.40 × 101 Bq/m3) were within the permissible limits set by the regulatory body. This report also confirmed that the estimated public dose levels (0.29 mSv/yr and 0.0002 mSv/yr) at the stack and ground positions were far below the IAEA acceptable limit (1.0 mSv/yr) which was significant for the research reactor safety.
{"title":"Experimental study of 41Ar activity release rate from the Bangladesh Atomic Energy Commission TRIGA research reactor","authors":"Md. Ajijul Hoq, Md. Abdul Malek Soner, M. Salam, Mizanur Rahman, N. Jahan","doi":"10.1504/ijnest.2020.10030870","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030870","url":null,"abstract":"The present study focused on the monthly or annual 41Ar activity release rate and ground level activity concentration measurement including the estimation of public dose level at the ground and stack positions of the Bangladesh Atomic Energy Commission TRIGA Research. During the experimental work, a Geiger-Muller (G-M) counter was used for the air sample count rate study. The experimental results demonstrated that the obtained maximum monthly or annual 41Ar activity release rate (2.48 × 1010 Bq/month or 6.25 × 1011 Bq/year) and monthly maximum ground level 41Ar activity concentration (6.40 × 101 Bq/m3) were within the permissible limits set by the regulatory body. This report also confirmed that the estimated public dose levels (0.29 mSv/yr and 0.0002 mSv/yr) at the stack and ground positions were far below the IAEA acceptable limit (1.0 mSv/yr) which was significant for the research reactor safety.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41778248","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030869
F. Al-Temimei, Malik S. Mhaimeed
In this study, a series of donor-π-acceptor systems were designed by introducing different π-bridges as functional groups. The geometric, electronic, quantum chemical, photovoltaic and absorption properties were investigated by the density functional theory (DFT) and time dependent-DFT method to approve which dyes show a good performance dye-sensitised solar cells. The six derivatives of organic D-π-A structures were studied, based on methyl substituted benzodithiophene as the donor group and ortho-fluorine-substituted phenyl, with cyanoacrylic acid as electron acceptor group with different π-bridges. The results expose that the introduction of the different π-bridge are more promising for formation of organic dyes with D-π-A arrangement. Also, the results found that the all dyes have better open circuit photovoltage, better light-harvesting efficiencies, higher electron injection efficiency and excellent photovoltaic efficiency. Therefore, these properties suggest that these new materials behave as better applicants and synthesis of photo-efficient dyes for sensitisers in DSSCs.
{"title":"Electronic structure, photovoltaic and absorption properties of designed photo-efficient new organic dyes with D-π-A framework","authors":"F. Al-Temimei, Malik S. Mhaimeed","doi":"10.1504/ijnest.2020.10030869","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030869","url":null,"abstract":"In this study, a series of donor-π-acceptor systems were designed by introducing different π-bridges as functional groups. The geometric, electronic, quantum chemical, photovoltaic and absorption properties were investigated by the density functional theory (DFT) and time dependent-DFT method to approve which dyes show a good performance dye-sensitised solar cells. The six derivatives of organic D-π-A structures were studied, based on methyl substituted benzodithiophene as the donor group and ortho-fluorine-substituted phenyl, with cyanoacrylic acid as electron acceptor group with different π-bridges. The results expose that the introduction of the different π-bridge are more promising for formation of organic dyes with D-π-A arrangement. Also, the results found that the all dyes have better open circuit photovoltage, better light-harvesting efficiencies, higher electron injection efficiency and excellent photovoltaic efficiency. Therefore, these properties suggest that these new materials behave as better applicants and synthesis of photo-efficient dyes for sensitisers in DSSCs.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46665544","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 : 2020-08-03DOI: 10.1504/ijnest.2020.10030866
Karen J. Dawson, P. Sabharwall
Construction costs constitute the largest outlay of a nuclear power plant. Direct costs, such as the cost of materials and installation of materials and equipment, make up the majority of construction expenditures. The purpose of this study is to quantify the cost of the two most abundant materials: concrete and steel. This study shows that a 1% reduction in concrete installation rate results in a 0.6% reduction in concrete costs, and a 1% reduction in the steel installation rate creates a 0.3% reduction in steel costs. The additional cost paid for nuclear-quality concrete is shown to be 23% of total concrete budget. The additional cost paid for nuclear-quality steel is shown to be 41% of the total steel expenditures. These results show that focus on decreasing commodity expenditures (through increasing installation rate) can improve the cost of constructing nuclear power plants.
{"title":"Light water reactor nuclear power plant commodity cost driver analysis","authors":"Karen J. Dawson, P. Sabharwall","doi":"10.1504/ijnest.2020.10030866","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030866","url":null,"abstract":"Construction costs constitute the largest outlay of a nuclear power plant. Direct costs, such as the cost of materials and installation of materials and equipment, make up the majority of construction expenditures. The purpose of this study is to quantify the cost of the two most abundant materials: concrete and steel. This study shows that a 1% reduction in concrete installation rate results in a 0.6% reduction in concrete costs, and a 1% reduction in the steel installation rate creates a 0.3% reduction in steel costs. The additional cost paid for nuclear-quality concrete is shown to be 23% of total concrete budget. The additional cost paid for nuclear-quality steel is shown to be 41% of the total steel expenditures. These results show that focus on decreasing commodity expenditures (through increasing installation rate) can improve the cost of constructing nuclear power plants.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-08-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45534151","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 : 2020-07-29DOI: 10.1504/ijnest.2020.10030871
B. Khuwaileh, Ahmad A. Ababneh
Verification and Validation (V&V) are the primary means to assess the accuracy and reliability in computational simulations which are used in the necessary practices of design, simulation and system optimisation. The main challenge is the ability to quantify the predictability of the model and establish an error upper bound in the V&V conclusions with a probabilistic statement. Therefore, this work introduces an iterative algorithm that quantifies the confidence in verification/validation conclusions and assigns a probabilistic statement given an error upper bound tolerance. Two case studies are used to illustrate and test the proposed algorithm. The first case study is a solution verification case study while the second is a simple validation-like case study. Results indicate that the proposed algorithm can help in assigning a violation probability estimate to certain error upper bound tolerance.
{"title":"Probabilistic error upper bounds for verification and validation practices for nuclear reactor modelling and simulation","authors":"B. Khuwaileh, Ahmad A. Ababneh","doi":"10.1504/ijnest.2020.10030871","DOIUrl":"https://doi.org/10.1504/ijnest.2020.10030871","url":null,"abstract":"Verification and Validation (V&V) are the primary means to assess the accuracy and reliability in computational simulations which are used in the necessary practices of design, simulation and system optimisation. The main challenge is the ability to quantify the predictability of the model and establish an error upper bound in the V&V conclusions with a probabilistic statement. Therefore, this work introduces an iterative algorithm that quantifies the confidence in verification/validation conclusions and assigns a probabilistic statement given an error upper bound tolerance. Two case studies are used to illustrate and test the proposed algorithm. The first case study is a solution verification case study while the second is a simple validation-like case study. Results indicate that the proposed algorithm can help in assigning a violation probability estimate to certain error upper bound tolerance.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49444731","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}
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