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Mitigation of end flux peaking in CANDU fuel bundles using neutron absorbers

  • Royal Military College of Canada
  • Canadian Nuclear Safety Commission

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

End flux peaking (EFP) is a phenomenon where a region of elevated neutron flux occurs between two adjoining fuel bundles. These peaks lead to an increase in fission rate and therefore greater heat generation. It is known that addition of neutron absorbers into fuel bundles can help mitigate EFP, yet implementation in Canada Deuterium Uranium (CANDU) type reactors using natural uranium fuel has not been pursued. Monte Carlo N-Particle code (MCNP) 6.1 was used to simulate the addition of a small amount of neutron absorbers strategically within the fuel pellets. This paper will present some preliminary results collected thus far.

Original languageEnglish
Title of host publicationCanadian Nuclear Society - 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015
PublisherCanadian Nuclear Society
Pages157-166
Number of pages10
ISBN (Electronic)9781510810815
StatePublished - 2015
Externally publishedYes
Event35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015 - Saint John, Canada
Duration: 31 May 20152 Jun 2015

Publication series

NameCanadian Nuclear Society - 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015
Volume1

Conference

Conference35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015
Country/TerritoryCanada
CitySaint John
Period31/05/152/06/15

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