Requirements for Extending the FAST Code for Transient Simulation of Nuclear Fuel

Abstract

The Fuel and Sheath modelling Tool (FAST) code is a finite-element model for the simulation of in-reactor fuel performance under Normal Operating Conditions (NOC) conditions. It has been tested and shows excellent agreement with other models and experimental results. This paper provides an overview of the steps necessary to extend the model for simulation of nuclear fuel during reactor transient or accident conditions. This would make the FAST code the first unified fuel performance model for CANDU fuel.