The paper presents new, transient simulation results of condensing steam in the event of emergency core cooling where water is injected into the cold leg during a postulated loss-of-coolant-accident (LOCA) of a pressurized water reactor (PWR), a phenomenon known as Pressurized Thermal Shock (PTS). The model is first validated for the Lim et al. (1984) experiment involving a smooth to wavy turbu...

Effect of pseudocritical rapid energy dissipation (PRED) from Pressurizer in nuclear steam supply system Pressurized Water Reactor, where a single event as common cause failure, considerable reduction base-load electricity demand causes the temperature reactor coolant (RCS) to increase, and corresponding pressure increases pressurizer generators above set-points. The study employed uses MATLAB/...

NEPTUNE_CFD is a code based on a 3D transient Eulerian two-fluid model. One of the main application targets is the two-phase Pressurized Thermal Shock (PTS), which is related to PWR Reactor Pressure Vessel (RPV) lifetime safety studies, when sub-cooled water from Emergency Core Cooling (ECC) system is injected into the possibly uncovered cold leg and penetrates into the RPV downcomer. Five expe...

This paper introduces the simulation, and controls using Simulink of MATLAB for PCTRAN (Personal Computer Transient Analysis) power control system (PWR) type pressurized water reactor PWR WESTINGHOUSE AP1000. The controller model produces mathematical description in nonlinear relation form which is an important popular program used at most universities education. described by a block diagram th...