Code and Solution Verification Assessment of the CTF Thermal Hydraulic Subchannel Code

Abstract

ABBREVIATIONS BEPU Best Estimate Plus Uncertainty CASL Consortium for Advanced Simulation of Light Water Reactors CHF critical heat flux CILC crud-induced localized corrosion CIPS crud-induced power shift CSAU Code Scaling, Applicability, and Uncertainty DNB departure from nucleate boiling EMDAP Evaluation Model Development and Assessment Process LBLOCA large-break loss-of-coolant accident LHS left-hand side LOCA loss-of-coolant accident NPP nuclear power plant PWR pressurized water reactor RHS right-hand side RIA reactivity insertion accident SQA software quality assurance TKE turbulent kinetic energy VERA Virtual Environment for Reactor Applications