Preliminary modelling of crack nucleation and propagation in SiC/SiC accident-tolerant fuel during routine operational transients using peridynamics
File(s)
Accepted version
Author(s)
Haynes, TA
Shepherd, D
Wenman, MR
Type
Journal Article
Abstract
Silicon carbide fibre in silicon carbide matrix composites (SiC/SiC) are a promising cladding for use in accident tolerant fuels (ATF) in current light water reactor (LWR) designs. However, as they are a radically different material from current metal clads, current thermomechanical simulation methods struggle to accurately predict their behaviour, especially regarding the potential development of cracks. Thus, a new peridynamic model for SiC/SiC cladding has been developed in the Abaqus finite element code. The material model was isotropic and considers matrix cracking and fibre pull-out. The thermal expansion, swelling and the degradation of the thermal conductivity are modelled under typical LWR irradiation conditions. The swelling on the outer surface is predicted to be greater than the inner surface due to the lower irradiation temperature, causing a tensile stress on the inside of the cladding; tension being more challenging for a ceramic than a metal. This stress increases during the decrease in power at the start of a typical pressurised water reactor refuelling outage and causes microcracking of the matrix on the cladding inner surface. In models without fibres, cracks would propagate through the cladding. If fibres are modelled, matrix cracking will extend to a depth of around 20% through the cladding from the inner surface, which is unlikely to be an acceptable design. If an inner monolith of SiC is additionally modelled, cracking propagates through the monolith and acts as a stress raiser for matrix cracking in the composite, and therefore does not constitute a design improvement. If an outer SiC monolith is modelled, fibre pull-out strain on the inner surface of the cladding was increased by just under 70%. No cracks are predicted in an outer monolith which may therefore remain gas-tight and thus a more suitable design. These predictions are consistent with experimental findings.
Date Issued
2020-11
Date Acceptance
2020-06-29
Citation
Journal of Nuclear Materials, 2020, 540
ISSN
0022-3115
Publisher
Elsevier BV
Journal / Book Title
Journal of Nuclear Materials
Volume
540
Copyright Statement
© 2020 Elsevier Ltd. All rights reserved. This manuscript is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International Licence http://creativecommons.org/licenses/by-nc-nd/4.0/
Sponsor
National Nuclear Laboratory (NNL)
Grant Number
1018536
Subjects
Science & Technology
Technology
Materials Science, Multidisciplinary
Nuclear Science & Technology
Materials Science
SILICON-CARBIDE
MECHANICAL-PROPERTIES
SIC COMPOSITES
NEUTRON-IRRADIATION
LWR APPLICATIONS
BEHAVIOR
CORROSION
TEMPERATURE
SENSITIVITY
STRENGTH
0912 Materials Engineering
Energy
Publication Status
Published
Article Number
152369
Date Publish Online
2020-07-09