Bundle geometry design influence on fuel burnup and performances in a CANDU reactor

摘要

The paper evaluates burnup and fuel performance aspects of some advanced CANada Deuterium Uranium (CANDU(1)) bundle geometry designs with more than 37 fuel elements and containing natural uranium dioxide pellets. Three advanced bundle geometries have been considered: the 43, 52 and 61-rods ones. Lattice calculations were performed to generate cross section tables with respect to the burnup and to find out instantaneous critical burnups. The burnup efficiency expressed as Uranium consumption for a reference period was evaluated through Core Follow Simulations (CFS). Outer element linear powers and power boosts together with thermo-mechanical parameters were calculated and discussed. The conclusions underline the burnup efficiency and associated uncertainties along with normal operation safety improvements brought by the advanced CANDU bundle geometry designs with increased numbers of fuel elements. Proposals for future work are made in order to get more reliable results using advanced modelling computer tools. (C) 2020 Elsevier Ltd. All rights reserved.