Removing Fuelling Transient Using Neutron Absorbers
Main Article Content
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.
Article Details
Section
Articles