A Study on the Core Characteristics for a CANDU 6 Reactor Fuelled with Recovered-Uranium CANFLEX Bundles

Abstract

A study on the core characteristics for CAW 6 reactor fuelled with reference (CANFLEX- RU) and low-void (version 1, CANFLEX-ST) fuels was performed. The time-average calculations with a 4-bundle shift fuelling scheme, the maximum bundle and channel powers of two fuel models have sufficient values to satisfy the design criteria of CANDU 6 reactor. The average exit burnups of two fuel models are over 50 % higher than that of CANFLEX-NU fuel. From the xenon transient calculations, the xenon load of two fuel models are lower than that of CANFLEX-NU fuel.