Analysis of Low Thermal-Conductivity Fuels in a 64-Element SCWR Bundle
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
G8-1 Supercritical Water Reactors

Authors:
Krysten King (University of Ontario Institute of Technology)
Shona Draper (University of Ontario Institute of Technology)
Wargha Peiman (University of Ontario Institute of Technology)
Ayman Abdalla (University of Ontario Institute of Technology)
Arif Qureshi (University of Ontario Institute of Technology)
Jon Joel (University of Waterloo)
Igor Pioro (University of Ontario Institute of Technology)
Kamiel Gabriel (University of Ontario Institute of Technology)
  

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. 

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