Requirements for Extending the FAST Code for Transient Simulation of Nuclear Fuel
36th Annual CNS-CNA Student Conference - 2012 June 12


Presented at:
36th Annual CNS-CNA Student Conference
2012 June 12
Location:
Saskatoon, Canada
Session Title:
CNS/CNA Student Conference 2012

Authors:
Andrew Prudil (Royal Military College of Canada )
Brent Lewis (Royal Military College of Canada )
Paul Chan (Royal Military College of Canada )
  

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.

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