Thermal-mechanical performance modeling of thorium-plutonium oxide fuel and comparison with on-line irradiation data
Journal article, 2015
Thorium-plutonium Mixed OXide (Th-MOX) fuel is considered for use in light water reactors fuel due to some inherent benefits over conventional fuel types in terms of neutronic properties. The good material properties of ThO2 also suggest benefits in terms of thermal-mechanical fuel performance, but the use of Th-MOX fuel for commercial power production demands that its thermal-mechanical behavior can be accurately predicted using a well validated fuel performance code. Given the scant operational experience with Th-MOX fuel, no such code is available today. This article describes the first phase of the development of such a code, based on the well-established code FRAPCON 3.4, and in particular the correlations reviewed and chosen for the fuel material properties. The results of fuel temperature calculations with the code in its current state of development are shown and compared with data from a Th-MOX test irradiation campaign which is underway in the Halden research reactor. The results are good for fresh fuel, whereas experimental complications make it difficult to judge the adequacy of the code for simulations of irradiated fuel. (C) 2015 Elsevier B.V. All rights reserved.
1964
x-ray
Processing
Nuclear fuel
conductivity
Materials Science
ikalla td
Thermal-mechanical performance
uo2-puo2 system
journal of nuclear materials
Thorium
Plutonium
expansion
FRAPCON
p131
v12
uo2
heat-capacity
dioxide
solid-solutions
Mining & Mineral
temperature
behavior
Nuclear Science & Technology
Author
Klara L Insulander Björk
Chalmers, Applied Physics, Nuclear Engineering
L. Kekkonen
Fortum Corporation
Institutt for energiteknikk
Journal of Nuclear Materials
0022-3115 (ISSN)
Vol. 467 876-885Subject Categories
Subatomic Physics
Metallurgy and Metallic Materials
DOI
10.1016/j.jnucmat.2015.11.001