Stability Analysis of Supercritical Water Natural Circulation Loop with Vertical Heater and Cooler
The idea of SCWR is an important incorporation in Generation- IV International Forum (GIF) nuclear reactor program. The SCWRs are the one of the six reactor innovations that are being examined broadly around the world. The present work demonstrates the computational investigation of ledinegg and density wave oscillation (DWO) instabilities in a supercritical water natural circulation loop with vertical heater and cooler (VHVCSCWNCL) using nonlinear 1-D thermal-hydraulic (TH) model. TH model is based on conservation equations of mass, momentum and energy. A rectangular VHVCSCWNCL has been investigated and wide computational simulations are performed to find the threshold stability boundary (TSB) in its relevant operating regime. Parametric studies are carried out to determine the effect of geometry like loop diameter and operating conditions like pressure, friction factor and loss of coefficient on the ledinegg and DWO instability.