Assessment of a Transuranic Mixed Oxide fuelled CANDU Reactor
34th Annual CNS Conference - 2013 June 09-12

Presented at:
34th Annual CNS Conference
2013 June 09-12
Toronto, Canada
Session Title:
Advanced Reactors and Fuels

Andrew C. Morreale (McMaster University)
John C. Luxat (McMaster University)
David R. Novog (McMaster University)


The extraction of transuranic actinides from spent fuel and use in current thermal reactors is an important step to providing an intermediary option before use in fast reactor fuel cycle in order to remove actinides from the nuclear waste stream.  A transuranic mixed oxide fuel can provide a high level of burnup and actinide reduction in a current CANDU®[1] reactor.  The effects of this fuel change on operations and performance must be assessed to ensure the reactor still operates within its designed envelope.  Operational evaluations of this fuel/reactor combination are made and compared to a standard natural uranium configuration detailing a similar performance envelope.

[1] CANadian Deuterium Uranium (CANDU) is a registered trademark of Atomic Energy of Canada Limited (AECL)

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.