The Effects of Fuel Burnup on Incremental Cross Sections in Actinide Fuels in CANDU Reactors
33rd Annual CNS Conference - 2012 June 10-13


Presented at:
33rd Annual CNS Conference
2012 June 10-13
Location:
Saskatoon, Canada
Session Title:
Physics-2

Authors:
Andrew C. Morreale (McMaster University)
Matthew R. Ball (McMaster University)
David R. Novog (McMaster University)
John C. Luxat (McMaster University)
  

Abstract

The burning of transuranic actinides from spent fuel in current thermal reactors is an active area of nuclear safety research. Mixed oxides can be used to combine actinides and natural uranium to produce a high burnup fuel suitable for use in CANDU® . Proper safety assessment is needed to ensure standard operational behavior is maintained with advanced fuels. The interaction of control devices with the fuel and the incremental cross sections should be explored over the full burnup cycle of the fuel to determine the changes that may result from composition changes in the fuel over the burnup lifetime.

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.