Author(s)

Frederick Agyemang¹, Stephen Yamoah^1,2, Seth Kofi Debrah^1,2

¹Graduate School of Nuclear and Allied Science, University of Ghana, Accra, Ghana.
²Nuclear Power Institute, Ghana Atomic Energy Commission, Accra, Ghana.

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.

Pseudocritical Rapid Energy Dissipation, Pseudocritical Saturation, Parameterization, Internal Energy, Pressure Vector, Heat Transfer Coefficient

Agyemang, F. , Yamoah, S. and Debrah, S. (2022) Pseudocritical Rapid Energy Dissipation Analysis of Base-Load Electrical Demand Reduction on Nuclear Steam Supply System. World Journal of Nuclear Science and Technology, 12, 69-87. doi: 10.4236/wjnst.2022.122007.