| People | Locations | Statistics |
|---|---|---|
| Naji, M. |
| |
| Motta, Antonella |
| |
| Aletan, Dirar |
| |
| Mohamed, Tarek |
| |
| Ertürk, Emre |
| |
| Taccardi, Nicola |
| |
| Kononenko, Denys |
| |
| Petrov, R. H. | Madrid |
|
| Alshaaer, Mazen | Brussels |
|
| Bih, L. |
| |
| Casati, R. |
| |
| Muller, Hermance |
| |
| Kočí, Jan | Prague |
|
| Šuljagić, Marija |
| |
| Kalteremidou, Kalliopi-Artemi | Brussels |
|
| Azam, Siraj |
| |
| Ospanova, Alyiya |
| |
| Blanpain, Bart |
| |
| Ali, M. A. |
| |
| Popa, V. |
| |
| Rančić, M. |
| |
| Ollier, Nadège |
| |
| Azevedo, Nuno Monteiro |
| |
| Landes, Michael |
| |
| Rignanese, Gian-Marco |
|
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
| Organizations | Location | People |
|---|
conferencepaper
Hafnium Oxidation in steam at high Temperature
Abstract
International audience ; Due to its high thermal neutron absorption cross section and good corrosion resistance at low temperature, hafnium has been used in the nuclear reactors as control rods or shut-off rods since the late 1950’s. Its use in commercial reactors declined in the 1990’s, due, in part, to its ability to pick-up hydrogen and swell. However, hafnium received a renewed interest, theses last years. For instance, in France, it is planned to generalize the introduction of absorber rods of hafnium not sheathed in fuel assemblies positioned in the core periphery in order to reduce the neutronic flux received by the vessel in the 900 MWe power plants. This paper presents IRSN and KIT results on the oxidation behaviour of hafnium up to 1400°C, i.e. in temperature conditions relevant to severe accidents. Samples, with different surface conditions (rods/tubes) were oxidized in steam/argon mixtures, either in a furnace or in a thermogravimetric analyser (TGA). Metallographic examinations, hydrogen measurements and Electron Probe Micro Analysis (EPMA) oxygen profiles were then performed. All the tests confirm that hafnium exhibits better resistance to oxidation at high temperature than zirconium alloys. For hafnium rods, metallographic examinations show the presence of a dense and protective oxide film, whereas, on hafnium tubes, a white and porous layer is observed. No or little hydrogen is measured in the metallic part of the rod specimens while significant hydrogen amount is picked up by hafnium tubes. Regarding hafnium rods, the reaction rate may be described by a parabolic law in the investigated temperature range, and the value determined from the experimental data in steam is in good agreement with the ones published in the literature for oxygen. The oxygen diffusion coefficient was estimated at each temperature by fitting the experimental profile obtained on hafnium rods. A linear regression of the data allows an estimate of the temperature dependence of the diffusion coefficient of oxygen in hafnium ...