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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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Barrachin, Marc
Institut de Radioprotection et de Sûreté Nucléaire
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (17/17 displayed)
- 2024Revisiting the thermodynamic properties of the ZrCr2 Laves phases by combined approach using experimental and simulation methodscitations
- 2021Hafnium Oxidation at High Temperature in Steamcitations
- 2019Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminumcitations
- 2019Interrupted heating DTA for liquidus temperature determination of Ag–Cd–In alloyscitations
- 2019Hafnium Oxidation in steam at high Temperature
- 2016Core melt composition at Fukushima Daiichi Results of transient simulations with ASTECcitations
- 2014Fuel and fission product behaviour in early phases of a severe accident. Part II Interpretation of the experimental results of the PHEBUS FPT2 testcitations
- 2014Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retentioncitations
- 2014Fuel and fission product behaviour in early phases of a severe accident. Part I Experimental results of the PHEBUS FPT2 testcitations
- 2013Late phase fuel degradation in the Phébus FP testscitations
- 2013Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle testscitations
- 2011Ternary eutectics in the systems FeO-UO2-ZrO2 and Fe2O3-U3O8-ZrO2citations
- 2011First-principles study of defect behavior in irradiated uranium monocarbidecitations
- 2007Phase diagram of the UO2-FeO1+x systemcitations
- 2007Progress in nuclear thermodynamic databanking for MCCI applications
- 2006Phase relations in the ZrO2-FeO systemcitations
- 2006Phase diagram of the ZrO2-FeO systemcitations
Places of action
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article
Hafnium Oxidation at High Temperature in Steam
Abstract
To assess the potential impact of using hafnium as absorber material in LWRs in high temperature accidental situations, the oxidation behavior of hafnium was studied up to 1400 °C, at temperature conditions relevant to severe accidents. Different sample geometries were used and samples oxidised in steam/argon mixtures, either in a furnace or in a thermogravimetric analyzer. Metallographic examinations, hydrogen measurements and EPMA oxygen profiles were then performed. For hafnium rods/discs, metallographic examinations showed the presence of a dense and protective oxide film after steam oxidation. No or little hydrogen was detected in the metallic part of the rod/disc specimens. The reaction rate can be described by a parabolic law in the tested temperature range in the mid-to-long term, and the value of the effective activation energy determined from the experimental data in steam is in good agreement with the ones published in the literature. The diffusion coeffcient of oxygen in hafnium was estimated at each temperature by fitting the experimental oxygen profile obtained on hafnium rods and its temperature dependence is given in the temperature range 700-1400 °C. The hafnium claddings produced for the application in integral bundle tests exhibited a lower resistance to steam oxidation than hafnium rods/discs. Metallographic examinations showed a non-protective layer and a significant hydrogen amount was picked up by hafnium tubes. Above 800 °C, the oxidation rate for hafnium tubes follows a cubic to quartic law and the effective activation energy was determined in the temperature range 800-1100 °C. These tests highlighted the influence of the surface conditions on the oxidation rate of hafnium in steam. However, hafnium oxidation rate remains well below the oxidation rate of zirconium alloys in the same temperature range.