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Abstract
In fuel behaviour modelling accurate description of the
cladding mechanical response is important for both
operational and safety considerations. While accuracy is
desired, a certain level of simplicity is needed as both
computational resources and detailed information on
properties of particular cladding may be limited. Most
models currently used in the integral codes divide the
mechanical response into elastic and viscoplastic
contributions. These have difficulties in describing both
creep and stress relaxation, and often separate models
for the two phenomena are used.
In this paper we implement anelastic contribution to the
cladding mechanical model, thus enabling consistent
modelling of both creep and stress relaxation. We show
that the model based on assumption of viscoelastic
behaviour can be used to explain several experimental
observations in transient situations and compare the
model to published set of creep and stress relaxation
experiments performed on similar samples. Based on the
analysis presented we argue that the inclusion of
anelastic contribution to the cladding mechanical models
provides a way to improve the simulation of cladding
behaviour during operational transients.
Original language | English |
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Pages (from-to) | 34-41 |
Journal | Journal of Nuclear Materials |
Volume | 465 |
DOIs | |
Publication status | Published - 2015 |
MoE publication type | A1 Journal article-refereed |
Keywords
- Zircaloy-4
- Cladding
- Stress relaxation
- Creep
- Anelastic
- Viscoelastic
- Modelling
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Dive into the research topics of 'Modelling anelastic contribution to nuclear fuel cladding creep and stress relaxation'. Together they form a unique fingerprint.Projects
- 1 Finished
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PANCHO - Physics and Chemistry of Nuclear Fuel
Tulkki, V., Loukusa, H., Heikinheimo, J., Peltonen, J., Arkoma, A., Myllykylä, E. & Pohja, R.
1/01/15 → 31/01/18
Project: Other