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
Saskatoon, Canada
Session Title:
CNS/CNA Student Conference 2012

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


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.

Individual Conference-Paper Copies (Electronic Where Available):

  • For CNS members, the first 5 copies per calendar year are free, and additional copies are $10 each.
  • For non-members, the price is $25 for the first Conference-paper copy in a request, and $10 each for additional copies of papers in the same conference and in the same request.
  • Contact the CNS office to order reprints.