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

Frederick Agyemang, S. Yamoah, S. K. Debrah
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引用次数: 0

Abstract

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 gene-rators 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.
核供汽系统基负荷电力需求降低的伪临界快速耗能分析
研究了压水堆核蒸汽供应系统中稳压器伪临界快速能量耗散(PRED)的影响,在单次共因故障时,基本负荷电力需求大幅减少,导致反应堆冷却剂系统(RCS)温度升高,相应的稳压器和蒸汽发生器压力高于设定值。本研究利用MATLAB/Simulink库工具,将压力控制实验建模为PRED,其中运动粘度分数在假临界点以上的输运动量作为多余能量耗散,以维持稳压器和RCS的安全,并保持水不沸腾。结果证明了压力矢量和普朗特数作为换热系数的重要性,它们提供了稳压器内流体的二维轮廓和三维比内能及其他参数化图形的详细活动。
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