SENSITIVITY ANALYSIS AND VERIFICATION OF FUEL ROD MODEL USED IN COUPLED NEUTRONIC AND THERMAL-HYDRAULIC CODES

L.M. Artemova, V.G. Artemov, and Yu.P. Shemayev Alexandrov Research Institute of Technology, Sosnovy Bor, Russia

17th Symposium of AER on VVER Reactor Physics and Reactor Safety (2007, Yalta, Crimea (Ukraine, back then))
CORE OPERATION, EXPERIMENTS AND CODE VALIDATION

Abstract

Realistic modeling of heat transfer in fuel rods is very important for coupled computer codes, because temperature-coefficient feedback is responsible for interfaces between neutronic and thermal-hydraulic parameters of VVER reactor core.

Presentation / full paper