effect of steam generator type on the dynamic behaviour of PWR system

this study considers the dynamic behaviour of steam generators as an integral component of the pressurized water reactor (PWR) nuclear steam supply system. two types of steam generators have been considered, namely the U - tube steam generator and the once-through steam generator, which are most common in PWR systems. a nonlinear dynamic model that fits for both types of steam generator has been developed using a state variable, moving boundary, lumped parameter technique. this model comprises 15 state variables representing the primary coolant temperatures, tube metal temperatures, and secondary fluid temperatures, pressure and boiling length