4th International Technical Meeting on Small Reactors - 2016 Nov. 02-04

Presented at:
4th International Technical Meeting on Small Reactors
2016 Nov. 02-04
Ottawa, ON Canada
Session Title:
Parallel Session A:3 - SMR Reactor Physics

D. Hummel (Canadian Nuclear Laboratories (CNL))


In reactor safety analysis the ‘source term’ is the amount of radioactivity available for release to the environment in the event of an accident. Knowledge of the source term is necessary to predict the radiological consequences of a postulated event. In turn, quantification of the source term requires knowledge on the amount of radionuclides present in the reactor and, most importantly, an understanding of the mechanisms in which they may be released to the environment. Mechanistic models have been developed to predict source terms in design basis accident and severe accident analyses of water-cooled reactors. However, several of the SMR concepts proposed for deployment in Canada are more advanced designs that eschew water coolant or even solid fuel. In this study three advanced SMR concepts were examined: a High Temperature Gas Reactor, a Lead-Cooled Fast Reactor, and a Molten Salt Reactor, to determine the mechanisms for radionuclide release and the hypothetical limiting (worst-case) accident with regards to source term for each.

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.