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Pseudocritical Rapid Energy Dissipation Analysis of Base-Load Electrical Demand Reduction on Nuclear Steam Supply System

Pseudocritical Rapid Energy Dissipation Analysis of Base-Load Electrical Demand Reduction on Nuclear Steam Supply System
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摘要 Effect of pseudocritical rapid energy dissipation (PRED) from Pressurizer in nuclear steam supply system of Pressurized Water Reactor, where a single event as common cause failure, of considerable reduction of base-load electricity demand causes the temperature of the reactor coolant system (RCS) to increase, and corresponding pressure increases in pressurizer and steam generators above set-points. The study employed the uses of MATLAB/Simulink library tools, to experimentally modelled pressure control as PRED, where the momentum of transport of kinematic viscosity fraction above pseudocritical point dissipated as excess energy, to maintain the safety of the Pressurizer and RCS and keep the water from boiling. The result demonstrated the significance of pressure vector and Prandlt number as heat transfer coefficients that provided detailed activities in 2-D contour and 3-D graphics of specific internal energy and other parameterization of fluid in the pressurizer. Effect of pseudocritical rapid energy dissipation (PRED) from Pressurizer in nuclear steam supply system of Pressurized Water Reactor, where a single event as common cause failure, of considerable reduction of base-load electricity demand causes the temperature of the reactor coolant system (RCS) to increase, and corresponding pressure increases in pressurizer and steam generators above set-points. The study employed the uses of MATLAB/Simulink library tools, to experimentally modelled pressure control as PRED, where the momentum of transport of kinematic viscosity fraction above pseudocritical point dissipated as excess energy, to maintain the safety of the Pressurizer and RCS and keep the water from boiling. The result demonstrated the significance of pressure vector and Prandlt number as heat transfer coefficients that provided detailed activities in 2-D contour and 3-D graphics of specific internal energy and other parameterization of fluid in the pressurizer.
作者 Frederick Agyemang Stephen Yamoah Seth Kofi Debrah Frederick Agyemang;Stephen Yamoah;Seth Kofi Debrah(Graduate School of Nuclear and Allied Science, University of Ghana, Accra, Ghana;Nuclear Power Institute, Ghana Atomic Energy Commission, Accra, Ghana)
出处 《World Journal of Nuclear Science and Technology》 2022年第2期69-87,共19页 核科学与技术国际期刊(英文)
关键词 Pseudocritical Rapid Energy Dissipation Pseudocritical Saturation PARAMETERIZATION Internal Energy Pressure Vector Heat Transfer Coefficient Pseudocritical Rapid Energy Dissipation Pseudocritical Saturation Parameterization Internal Energy Pressure Vector Heat Transfer Coefficient
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