Removing Fuelling Transient Using Neutron Absorbers

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Stephane Paquette
Paul K. Chan
H.W. Bonin
A. Pant

Abstract

Preliminary results indicate that by selecting a small amount of neutron absorber the fuelling transient, currently occurring in a CANDU 37-element fuel bundle, can be successfully removed. A parametric study using the Los Alamos National Laboratories' MCNP 5 code and Atomic Energy of Canada Limited's WIMS AECL 3.1 is presented in this paper.

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