The Experts below are selected from a list of 79449 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.
Matthias Wessling - One of the best experts on this subject based on the ideXlab platform.
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beyond the catalyst how electrode and Reactor Design determine the product spectrum during electrochemical co2 reduction
Chemical Engineering Journal, 2019Co-Authors: Janbernd Vennekoetter, Robert Sengpiel, Matthias WesslingAbstract:Abstract As a remedy to the increasing concentration of greenhouse gases and depleting fossil resources, the electrochemical CO2 reduction closes the carbon cycle and provides an alternative carbon feedstock to the chemical and energy industry. While most contemporary research focuses on the catalyst activity, we emphasize the importance of the Reactor Design for an energetic efficient (EE) conversion. A Design strategy for an electrochemical membrane Reactor reducing CO2 to hydrogen, carbon monoxide (CO) and ethylene (C2H4) is developed. We present the stepwise development from an H-cell like setup using full-metal electrodes to a cell with gas diffusion electrodes (GDE) towards high current efficiencies (CE) at high current densities (CD). At 300 mA.cm−2 a CO-CE of 56% for a Ag GDE and a C2H4-CE of 94% for a Cu GDE are measured. The incorporation of the developed GDEs into a zero-gap assembly eliminates ohmic losses and maximizes EE, however the acidic environment of the ion exchange membrane inhibits CO2 reduction. As a compromise a thin liquid buffer layer between cathode and membrane is a prerequisite for a highly active conversion. We demonstrate that industrial relevant CDs with high CEs and EEs can only be achieved by moving beyond today’s research form catalyst development only to an integrated Reactor Design, which allows to exploit the viable potential of electrochemical CO2 reduction catalysts.
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.
Samuel S. Stewart - One of the best experts on this subject based on the ideXlab platform.
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Reactor Design of the SP-100 nuclear assembly test
AIP Conference Proceedings, 1991Co-Authors: Charles L. Cowan, Alan Chung, Samuel Kaplan, Thomas F. Marcille, Robert Protsik, Samuel S. StewartAbstract:The Nuclear Assembly Test is currently being Designed to demonstrate the performance characteristics of a 100‐kWe version of the power source for the SP‐100 Generic Flight System. Particular emphasis will be placed upon the operation of the prototypical ground test Reactor under conditions of high‐working temperatures and long life. The key features of the Reactor include a small, compact core with component materials consisting of refractory metals and alloys. Because of the unique features of the SP‐100 system, extensive use is made of Monte Carlo methods in the Design and analysis of the Reactor configuration. In addition, detailed testing of the Reactor Design has been carried out in the Zero Power Physics Reactor facility to provide calibration factors for the principal performance parameters. The key features of the test Reactor Design are described in this paper.
M.n. Agu - 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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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.
