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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Rantala, Juhani
VTT Technical Research Centre of Finland
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (25/25 displayed)
- 2024Crystal plasticity model for creep and relaxation deformation of OFP coppercitations
- 2023Crystal plasticity model for creep and relaxation deformation of OFP coppercitations
- 2021Creep properties of 9Cr and 14Cr ODS tubes tested by inner gas pressurecitations
- 2018Experimentally verified model based predictions for integrity of copper overpack:Annual report 2017
- 2018Experimentally verified model based predictions for integrity of copper overpack
- 2017Microstructural and mechanical characterization of ODS alloy produced by surface oxidation method
- 2016Multiaxial creep testing device for nuclear fuel claddings
- 2016Relaxation behaviour of copper in disposal canisters
- 2016Impression creep testing for the HAZ of a P22 weld
- 2016Creep performance of fuel cladding
- 2016Creep analyses of a steam pipe system
- 2015Material integrity of welded copper overpack:Annual report 2014
- 2015Material integrity of welded copper overpack
- 2013Creep damage and long term life modelling of an X20 steam line componentcitations
- 2013Practical application of impression creep data to power plant
- 2013Performance of copper overpack for repository canisters
- 2010Creep damage and long term life of steam line components
- 2010Mechanical performance and life prediction for canister copper
- 2010Creep damage and long term life of steam line components:Case X20
- 2009Modeling and verification of creep strain and exhaustion in a welded steam mixercitations
- 2008Modelling and verification of creep strain and exhaustion in a welded steam mixer
- 2008Creep damage, ductility and expected life for materials with defects
- 2007The LICON approach to life management
- 2001Modelling the development of creep damage:The licon experience
- 2001Modelling the development of creep damage
Places of action
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document
Creep performance of fuel cladding
Abstract
The understanding of the creep behavior of nuclear fuelcladdings is essential to predict safely and reliably thethermal performance and mechanical integrity of fuelrods. Fuel cladding tubes experience a range of changingconditions during their reactor life, furthercomplicating the analysis. Today's nuclear reactorswidely use zirconium alloys as fuel cladding material.Zirconium alloys exhibit anisotropic creep properties andtheir creep behavior depends significantly on thematerial condition. As for envisaged Gen-IV reactors,modified austenitic stainless steels and ODS alloys arecandidate materials for claddings because of highertemperatures expected in operating conditions. This paperdescribes the research activities related to the creepbehavior of cladding materials carried out at VTT. Theseactivities include experimental research using the newlydeveloped Pneumatic Loading Apparatus (PLA), which iscapable of testing the steady state and transient creepproperties of fuel cladding specimens with internalpressure of up to 700 bar and an additional axial forceof up to 4 kN in tensile or compressive direction.Furthermore, creep models for cladding materials arebeing developed using viscoelastic modelling approach andLogistic Creep Strain Prediction (LCSP) method.