Analysis of Low Thermal-Conductivity Fuels in a 64-Element SCWR Bundle

Abstract

The objective of this study is to examine the possibility of using nuclear fuels with low thermal-conductivities (UO₂, ThO₂, and MOX) in order to compare fuel options for use in a SuperCritical Water-cooled Reactor (SCWR). The bundle being analyzed will be a 64-element fuel bundle containing 63 heated elements (9.13-mm OD) and one central unheated element (20-mm OD). When UO₂ is utilized as a fuel in a generic 43-element bundle (11.5-mm OD), the fuel centerline temperature may exceed the industry accepted limit of 1850°C for certain Axial Heat Flux Profiles (AHFPs). The 64-element fuel bundle showed promising results at SCWR conditions with the use of low thermal-conductivity fuels with various AHFPs.