MITIGATION OF END FLUX PEAKING IN CANDU FUEL BUNDLES USING NEUTRON ABSORBERS
35th Annual CNS Conference - 2015 May 31 - June 3


Presented at:
35th Annual CNS Conference
2015 May 31 - June 3
Location:
Saint John, Canada
Session Title:
1A4 - Nuclear Materials

Authors:
D. Pierce (Royal Military College of Canada)
P. K. Chan (Royal Military College of Canada)
W. Shen (Canadian Nuclear Safety Commission)
  

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.

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