The Experts below are selected from a list of 189 Experts worldwide ranked by ideXlab platform
P.o. Akusu - One of the best experts on this subject based on the ideXlab platform.
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Comparative Analysis of Water-Cooled Reactor Design Models and Gas-Cooled Reactor Design Models
Journal of Energy Technologies and Policy, 2013Co-Authors: A.i. Oludare, M.n. Agu, P.o. Akusu, O. E. OmolaraAbstract:To determined the most stable and probably the safest Reactor between water-cooled Reactor designs and gas-cooled Reactor designs in terms of their coolant, Linear Regression Analysis is applied on four typical Nuclear Reactor design models, viz water-cooled Reactor design I (WCRD I), water-cooled Reactor design II (WCRD II), gas-cooled Reactor design I (GCRD I) and gas-cooled Reactor design II (GCRD II). Empirical expressions are obtained for WCRD I model, WCRD II model, GCRD I model and GCRD II model. The results of the statistical analyses on these four types of Nuclear Reactor models reveal that the GCRD II promises to be most stable. The implication of this research effort to Nigeria’s Nuclear Power project is discussed. Keywords: Linear Regression Analysis, Water-Cooled Reactor Design Models, Gas-Cooled Reactor Design Models, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Designs
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Study of Pressurized Water Reactor Design Models
Innovative Systems Design and Engineering, 2013Co-Authors: A.i. Oludare, P.o. AkusuAbstract:This study of pressurized water Reactor design models involves the application of linear regression analysis on two typical Water-Cooled Nuclear Reactor design models, viz Pressurized Water Reactor Design I (PWRD I) and Pressurized Water Reactor Design II (PWRD II). Empirical expressions are obtained for PWRD I model and PWRD II model. The results of the statistical analyses on these two types of Nuclear Reactor models reveal that the PWRD II promises to be more stable and therefore safer. The implication of this research effort to Nigeria’s Nuclear Power project is discussed. Keywords: Linear Regression Analysis, Pressurized Water Reactor Design Models, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Designs
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Stability Margin Analysis of Gas-Cooled Reactor Design Models
Mathematical theory and modeling, 2013Co-Authors: A.i. Oludare, M.n. Agu, P.o. AkusuAbstract:To determined the safety margin of different Gas-Cooled Reactor Design, linear regression analysis is applied on three typical Gas-Cooled Nuclear Reactor design models, viz Gas-Cooled Reactor Design I (GCRD I), Gas-cooled Reactor Design II (GCRD II) and Gas-cooled Reactor Design III (GCRD III). Empirical expressions are obtained for GCRD I model, GCRD II model and GCRD III model. The results of the statistical analyses on these three types of Nuclear Reactor models reveal that the GCRD III promises to be most stable and therefore safer. The implication of this research effort to Nigeria’s Nuclear Power project is discussed. Keywords: Linear Regression Analysis, Gas-Cooled Reactor Design Models, Safety Margin, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Design Models.
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Optimization of the Stability Margin for Nuclear Power Reactor Design Models Using Regression Analyses Techniques
Journal of Nuclear and Particle Physics, 2013Co-Authors: A.i. Oludare, M.n. Agu, P.o. AkusuAbstract:Multiple regression analysis is applied on twenty-four (24) typical Nuclear Reactor design models, each having sixt een (16) major design input parameters. An emp irical expression for "Safety Factor", Ỳ, as a function of the sixteen major design input parameters is obtained. Further statistical analyses suggest that this empirical exp ression is acceptable as the calculated values of Ỳ is in good agreement with known typical values. 78.95% of the "Safety Factor", Ỳ, is observed fro m the sixteen major design input parameters at significant level of 5%. This shows that the regression analyses techniques may be applied as an effective tool fo r optimization of the stability margin in Nuclear Power Reactor design models.
Sooill Lee - One of the best experts on this subject based on the ideXlab platform.
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Design of the Cognitive Information Display for Water Level Control of the Steam Generator in Korean Nuclear Power Reactor
2012Co-Authors: Sooill LeeAbstract:This paper introduces a design of the cognitive information display using EID (Ecological Interface Design) for the water level control of steam generator in Korean advance Nuclear Power Reactor. The concept of conventional display method in NPPs (Nuclear Power Plants) mainly relies on the SSSI (Single Sensor Single Indicator) design criteria; therefore, the conventional information display method employed a method based on the type of P&ID (Piping & Instrumentation Diagram). Due to the lack or excess of the information, the operators in NPPs could not understand the overall relationship between the objective and operator’s control; it leads to be a human’s cognitive decision burden and human error. In this paper, we propose the design method that applies the EID to the water level control of steam generator in advanced Nuclear Power Reactor. This design method consists of the cognitive task analysis, the selection of the example task, the design of the example task, the feasibility evaluation. Proposed design method shows the effectiveness when developing the cognitive information display in NPPs. Also, this paper shows the further study points not only for applying the EID to real NPPs, but also for applying the EID to ubiquitous maintenance applications in real NPPs to overcome the lack of the information due to small screen.
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NPC - Design of the Cognitive Information Display for Water Level Control of the Steam Generator in Korean Nuclear Power Reactor
Lecture Notes in Computer Science, 2012Co-Authors: Sooill LeeAbstract:This paper introduces a design of the cognitive information display using EID (Ecological Interface Design) for the water level control of steam generator in Korean advance Nuclear Power Reactor. The concept of conventional display method in NPPs (Nuclear Power Plants) mainly relies on the SSSI (Single Sensor Single Indicator) design criteria; therefore, the conventional information display method employed a method based on the type of PI it leads to be a human’s cognitive decision burden and human error. In this paper, we propose the design method that applies the EID to the water level control of steam generator in advanced Nuclear Power Reactor. This design method consists of the cognitive task analysis, the selection of the example task, the design of the example task, the feasibility evaluation. Proposed design method shows the effectiveness when developing the cognitive information display in NPPs. Also, this paper shows the further study points not only for applying the EID to real NPPs, but also for applying the EID to ubiquitous maintenance applications in real NPPs to overcome the lack of the information due to small screen.
M Deniz - One of the best experts on this subject based on the ideXlab platform.
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constraints on non standard neutrino interactions and unparticle physics with neutrino electron scattering at the kuo sheng Nuclear Power Reactor
Physical Review D, 2010Co-Authors: M Deniz, H B Li, S Bilmis, I O Yildirim, Jian Li, H Y LiaoAbstract:Neutrino-electron scatterings are purely leptonic processes with robust standard model (SM) predictions. Their measurements can therefore provide constraints to physics beyond SM. The {nu}{sub e}-e data taken at the Kuo-Sheng Reactor Neutrino Laboratory were used to probe two scenarios: nonstandard neutrino interactions (NSI) and unparticle physics. New constraints were placed on the NSI parameters ({epsilon}{sub ee}{sup eL},{epsilon}{sub ee}{sup eR}), ({epsilon}{sub e{mu}}{sup eL},{epsilon}{sub e{mu}}{sup eR}), and ({epsilon}{sub e{tau}}{sup eL},{epsilon}{sub e{tau}}{sup eR}) for the nonuniversal and flavor-changing channels, respectively, as well as to the coupling constants for scalar ({lambda}{sub 0}) and vector ({lambda}{sub 1}) unparticles to the neutrinos and electrons.
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search for axions from the kuo sheng Nuclear Power Reactor with a high purity germanium detector
Physical Review D, 2007Co-Authors: H M Chang, H T Wong, M H Chou, M Deniz, H X Huang, H B Li, J C Li, H Y LiaoAbstract:A search of axions produced in Nuclear transitions was performed at the Kuo-Sheng Nuclear Power Station with a high-purity germanium detector of mass 1.06 kg at a distance of 28 m from the 2.9 GW Reactor core. The expected experimental signatures were monoenergetic lines produced by their Primakoff or Compton conversions at the detector. Based on 459.0/96.3 days of Reactor ON/OFF data, no evidence of axion emissions were observed and constraints on the couplings g{sub a{gamma}}{sub {gamma}} and g{sub aee} versus axion mass m{sub a} within the framework of invisible axion models were placed. The KSVZ and DFSZ models can be excluded for 10{sup 4} eV < or approx. m{sub a} < or approx. 10{sup 6} eV. Model-independent constraints on g{sub a{gamma}}{sub {gamma}}{center_dot}g{sub aNN}{sup 1}<7.7x10{sup -9} GeV{sup -2} for m{sub a} < or approx. 10{sup 5} eV and g{sub aee}{center_dot}g{sub aNN}{sup 1}<1.3x10{sup -10} for m{sub a} < or approx.10{sup 6} eV at 90% confidence level were derived. This experimental approach provides a unique probe for axion mass at the keV-MeV range not accessible to the other techniques.
H Y Liao - One of the best experts on this subject based on the ideXlab platform.
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constraints on non standard neutrino interactions and unparticle physics with neutrino electron scattering at the kuo sheng Nuclear Power Reactor
Physical Review D, 2010Co-Authors: M Deniz, H B Li, S Bilmis, I O Yildirim, Jian Li, H Y LiaoAbstract:Neutrino-electron scatterings are purely leptonic processes with robust standard model (SM) predictions. Their measurements can therefore provide constraints to physics beyond SM. The {nu}{sub e}-e data taken at the Kuo-Sheng Reactor Neutrino Laboratory were used to probe two scenarios: nonstandard neutrino interactions (NSI) and unparticle physics. New constraints were placed on the NSI parameters ({epsilon}{sub ee}{sup eL},{epsilon}{sub ee}{sup eR}), ({epsilon}{sub e{mu}}{sup eL},{epsilon}{sub e{mu}}{sup eR}), and ({epsilon}{sub e{tau}}{sup eL},{epsilon}{sub e{tau}}{sup eR}) for the nonuniversal and flavor-changing channels, respectively, as well as to the coupling constants for scalar ({lambda}{sub 0}) and vector ({lambda}{sub 1}) unparticles to the neutrinos and electrons.
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search for axions from the kuo sheng Nuclear Power Reactor with a high purity germanium detector
Physical Review D, 2007Co-Authors: H M Chang, H T Wong, M H Chou, M Deniz, H X Huang, H B Li, J C Li, H Y LiaoAbstract:A search of axions produced in Nuclear transitions was performed at the Kuo-Sheng Nuclear Power Station with a high-purity germanium detector of mass 1.06 kg at a distance of 28 m from the 2.9 GW Reactor core. The expected experimental signatures were monoenergetic lines produced by their Primakoff or Compton conversions at the detector. Based on 459.0/96.3 days of Reactor ON/OFF data, no evidence of axion emissions were observed and constraints on the couplings g{sub a{gamma}}{sub {gamma}} and g{sub aee} versus axion mass m{sub a} within the framework of invisible axion models were placed. The KSVZ and DFSZ models can be excluded for 10{sup 4} eV < or approx. m{sub a} < or approx. 10{sup 6} eV. Model-independent constraints on g{sub a{gamma}}{sub {gamma}}{center_dot}g{sub aNN}{sup 1}<7.7x10{sup -9} GeV{sup -2} for m{sub a} < or approx. 10{sup 5} eV and g{sub aee}{center_dot}g{sub aNN}{sup 1}<1.3x10{sup -10} for m{sub a} < or approx.10{sup 6} eV at 90% confidence level were derived. This experimental approach provides a unique probe for axion mass at the keV-MeV range not accessible to the other techniques.
A.i. Oludare - One of the best experts on this subject based on the ideXlab platform.
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Comparative Analysis of Water-Cooled Reactor Design Models and Gas-Cooled Reactor Design Models
Journal of Energy Technologies and Policy, 2013Co-Authors: A.i. Oludare, M.n. Agu, P.o. Akusu, O. E. OmolaraAbstract:To determined the most stable and probably the safest Reactor between water-cooled Reactor designs and gas-cooled Reactor designs in terms of their coolant, Linear Regression Analysis is applied on four typical Nuclear Reactor design models, viz water-cooled Reactor design I (WCRD I), water-cooled Reactor design II (WCRD II), gas-cooled Reactor design I (GCRD I) and gas-cooled Reactor design II (GCRD II). Empirical expressions are obtained for WCRD I model, WCRD II model, GCRD I model and GCRD II model. The results of the statistical analyses on these four types of Nuclear Reactor models reveal that the GCRD II promises to be most stable. The implication of this research effort to Nigeria’s Nuclear Power project is discussed. Keywords: Linear Regression Analysis, Water-Cooled Reactor Design Models, Gas-Cooled Reactor Design Models, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Designs
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Study of Pressurized Water Reactor Design Models
Innovative Systems Design and Engineering, 2013Co-Authors: A.i. Oludare, P.o. AkusuAbstract:This study of pressurized water Reactor design models involves the application of linear regression analysis on two typical Water-Cooled Nuclear Reactor design models, viz Pressurized Water Reactor Design I (PWRD I) and Pressurized Water Reactor Design II (PWRD II). Empirical expressions are obtained for PWRD I model and PWRD II model. The results of the statistical analyses on these two types of Nuclear Reactor models reveal that the PWRD II promises to be more stable and therefore safer. The implication of this research effort to Nigeria’s Nuclear Power project is discussed. Keywords: Linear Regression Analysis, Pressurized Water Reactor Design Models, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Designs
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Stability Margin Analysis of Gas-Cooled Reactor Design Models
Mathematical theory and modeling, 2013Co-Authors: A.i. Oludare, M.n. Agu, P.o. AkusuAbstract:To determined the safety margin of different Gas-Cooled Reactor Design, linear regression analysis is applied on three typical Gas-Cooled Nuclear Reactor design models, viz Gas-Cooled Reactor Design I (GCRD I), Gas-cooled Reactor Design II (GCRD II) and Gas-cooled Reactor Design III (GCRD III). Empirical expressions are obtained for GCRD I model, GCRD II model and GCRD III model. The results of the statistical analyses on these three types of Nuclear Reactor models reveal that the GCRD III promises to be most stable and therefore safer. The implication of this research effort to Nigeria’s Nuclear Power project is discussed. Keywords: Linear Regression Analysis, Gas-Cooled Reactor Design Models, Safety Margin, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Design Models.
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Optimization of the Stability Margin for Nuclear Power Reactor Design Models Using Regression Analyses Techniques
Journal of Nuclear and Particle Physics, 2013Co-Authors: A.i. Oludare, M.n. Agu, P.o. AkusuAbstract:Multiple regression analysis is applied on twenty-four (24) typical Nuclear Reactor design models, each having sixt een (16) major design input parameters. An emp irical expression for "Safety Factor", Ỳ, as a function of the sixteen major design input parameters is obtained. Further statistical analyses suggest that this empirical exp ression is acceptable as the calculated values of Ỳ is in good agreement with known typical values. 78.95% of the "Safety Factor", Ỳ, is observed fro m the sixteen major design input parameters at significant level of 5%. This shows that the regression analyses techniques may be applied as an effective tool fo r optimization of the stability margin in Nuclear Power Reactor design models.
