Coupling of Reactor Physics and Thermalhydraulics Codes for CANDU Analysis

Abstract

A coupled thermal-hydraulics and reactor physics simulation procedure was recently developed. It uses ASSERT-PV and the reactor core code chain DRAGON/DONJON/NDF developed at IGN. Parts of these programs where adapted to be run within a coupling procedure written in the GAN generalized driver environment. As a first test, the process was used to simulate one channel (channel NII) in a nominal reactor core similar to a CANDU-6. The coupled results are compared with a regular stand alone reactor physics calculation of the same core.