Materials Map

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The Materials Map is an open tool for improving networking and interdisciplinary exchange within materials research. It enables cross-database search for cooperation and network partners and discovering of the research landscape.

The dashboard provides detailed information about the selected scientist, e.g. publications. The dashboard can be filtered and shows the relationship to co-authors in different diagrams. In addition, a link is provided to find contact information.

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The Materials Map is still under development. In its current state, it is only based on one single data source and, thus, incomplete and contains duplicates. We are working on incorporating new open data sources like ORCID to improve the quality and the timeliness of our data. We will update Materials Map as soon as possible and kindly ask for your patience.

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Institut de Radioprotection et de Sûreté Nucléaire

in Cooperation with on an Cooperation-Score of 37%

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Publications (17/17 displayed)

  • 2024Revisiting the thermodynamic properties of the ZrCr2 Laves phases by combined approach using experimental and simulation methods3citations
  • 2021Hafnium Oxidation at High Temperature in Steam8citations
  • 2019Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminum6citations
  • 2019Interrupted heating DTA for liquidus temperature determination of Ag–Cd–In alloys8citations
  • 2019Hafnium Oxidation in steam at high Temperaturecitations
  • 2016Core melt composition at Fukushima Daiichi Results of transient simulations with ASTEC9citations
  • 2014Fuel and fission product behaviour in early phases of a severe accident. Part II Interpretation of the experimental results of the PHEBUS FPT2 test7citations
  • 2014Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention8citations
  • 2014Fuel and fission product behaviour in early phases of a severe accident. Part I Experimental results of the PHEBUS FPT2 test14citations
  • 2013Late phase fuel degradation in the Phébus FP tests26citations
  • 2013Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests26citations
  • 2011Ternary eutectics in the systems FeO-UO2-ZrO2 and Fe2O3-U3O8-ZrO210citations
  • 2011First-principles study of defect behavior in irradiated uranium monocarbide45citations
  • 2007Phase diagram of the UO2-FeO1+x system34citations
  • 2007Progress in nuclear thermodynamic databanking for MCCI applicationscitations
  • 2006Phase relations in the ZrO2-FeO system18citations
  • 2006Phase diagram of the ZrO2-FeO system53citations

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Cui, Jinjiang
1 / 1 shared
Mikaelian, Georges
3 / 7 shared
Touzin, Matthieu
1 / 18 shared
Tougait, Olivier
1 / 28 shared
Ducher, Roland
1 / 1 shared
Benigni, Pierre
2 / 3 shared
Tanguy, Céline
2 / 2 shared
Steinbrueck, Martin
2 / 11 shared
Stuckert, Juri
2 / 16 shared
Guilbert, Severine
2 / 8 shared
Viretto, Alice
2 / 4 shared
Janghorban, A.
1 / 1 shared
Decreton, A.
1 / 2 shared
Fischer, E.
1 / 4 shared
Virot, François
1 / 2 shared
Antion, C.
1 / 3 shared
Gajavalli, K.
1 / 3 shared
Rogez, Jacques
2 / 6 shared
Lomello-Tafin, M.
1 / 3 shared
Benigni, P.
1 / 9 shared
Decreton, Alexandre
1 / 1 shared
Gajavalli, Kasi
1 / 2 shared
Fischer, Evelyne
2 / 4 shared
Bonneville, H.
1 / 1 shared
Carenini, L.
1 / 2 shared
Gavillet, D.
2 / 4 shared
Ducher, R.
2 / 4 shared
Bremaecker, A. De
2 / 5 shared
Dubourg, R.
3 / 6 shared
Sulatsky, A. A.
1 / 1 shared
Vitol, S. A.
5 / 5 shared
Piluso, P.
1 / 11 shared
Granovsky, V. S.
1 / 1 shared
Fischer, M.
3 / 16 shared
Bottomley, P. D.
1 / 1 shared
Gusarov, V. V.
5 / 5 shared
Almjashev, V. I.
4 / 4 shared
Bechta, S. V.
4 / 4 shared
Khabensky, V. B.
4 / 4 shared
Krushinov, E. V.
5 / 5 shared
Repetto, G.
2 / 4 shared
Haste, T.
2 / 5 shared
Luze, O. De
2 / 2 shared
Bottomley, D.
3 / 3 shared
Petrov, Y. B.
1 / 2 shared
Lysenko, A. V.
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Hellmann, S.
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Lopukh, D. B.
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Mezentseva, L. P.
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Fisher, M.
1 / 2 shared
Petrov, Yu. B.
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1 / 1 shared
Cheynet, Bertrand
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Almyashev, V. I.
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Beshta, S. V.
1 / 1 shared
Khabenskii, V. B.
1 / 1 shared
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2024
2021
2019
2016
2014
2013
2011
2007
2006

Co-Authors (by relevance)

  • Cui, Jinjiang
  • Mikaelian, Georges
  • Touzin, Matthieu
  • Tougait, Olivier
  • Ducher, Roland
  • Benigni, Pierre
  • Tanguy, Céline
  • Steinbrueck, Martin
  • Stuckert, Juri
  • Guilbert, Severine
  • Viretto, Alice
  • Janghorban, A.
  • Decreton, A.
  • Fischer, E.
  • Virot, François
  • Antion, C.
  • Gajavalli, K.
  • Rogez, Jacques
  • Lomello-Tafin, M.
  • Benigni, P.
  • Decreton, Alexandre
  • Gajavalli, Kasi
  • Fischer, Evelyne
  • Bonneville, H.
  • Carenini, L.
  • Gavillet, D.
  • Ducher, R.
  • Bremaecker, A. De
  • Dubourg, R.
  • Sulatsky, A. A.
  • Vitol, S. A.
  • Piluso, P.
  • Granovsky, V. S.
  • Fischer, M.
  • Bottomley, P. D.
  • Gusarov, V. V.
  • Almjashev, V. I.
  • Bechta, S. V.
  • Khabensky, V. B.
  • Krushinov, E. V.
  • Repetto, G.
  • Haste, T.
  • Luze, O. De
  • Bottomley, D.
  • Petrov, Y. B.
  • Lysenko, A. V.
  • Hellmann, S.
  • Lopukh, D. B.
  • Miassoedov, A.
  • Defoort, F.
  • Mezentseva, L. P.
  • Martynov, A. P.
  • Pasturel, A.
  • Tromm, W.
  • Froment, K.
  • Fisher, M.
  • Petrov, Yu. B.
  • Chevalier, Pierre-Yves
  • Cheynet, Bertrand
  • Almyashev, V. I.
  • Beshta, S. V.
  • Khabenskii, V. B.
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article

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

  • Repetto, G.
  • Barrachin, Marc
  • Haste, T.
  • Luze, O. De
Abstract

The international Phébus Fission Product Programme investigated key phenomena occurring in light water reactor core meltdown accidents in a series of five in-pile experiments. Four of these tests focused on the degradation of fuel rod bundles, containing a central control rod, and on the resulting release of fission products, structural materials and actinides from the fuel rod bundle, their transport in the reactor coolant system (RCS) and their subsequent behaviour in the containment vessel. Various steam contents were used in the RCS, from highly oxidising conditions (in FPT0 and FPT1) to more reducing ones (in FPT2 and FPT3). The "early degradation phase" took place at the beginning of the Phébus driver core and fuel bundle heat-up phase, with a quasi-intact fuel bundle geometry. During this phase, the degradation of the control rod and the oxidation runaway due to the fast oxidation of the Zircaloy claddings of the fuel rods, were two major events which took place. The oxidation runaway locally increased the temperatures much above the temperatures resulting from the Phébus driver core heat transfer to the bundle and yielded a large hydrogen release, which amounted to 70-80% of the whole hydrogen production during the tests. The maximum hydrogen flow rates increased with increasing steam flow rates injected at the fuel bundle inlet. The failure mechanisms of silver-indium-cadmium (used in three tests) and boron carbide (used in one test) control rods involve eutectic interactions amongst the components of these control rods. Mechanical deformations of the control rod stainless steel cladding against the Zircaloy control rod guide tube are the main presumed mechanisms for the beginning of these eutectic formations. However, different post-failure scenarios can be postulated for the effect of control rod degradation on fuel bundle degradation for both types of control rods. The exothermic oxidation of the exposed boron carbide pellets led to the release of carbonaceous species (CO, CO2) as well as of additional hydrogen, but no significant methane release could be detected above the limits of detection. Overall, the results confirmed existing knowledge concerning early phase degradation phenomenology found in previous integral experiments such as CORA and QUENCH (Karlsruhe Institute of Technology) and Phébus SFD (IRSN Cadarache), and formed a sound basis for analysis of the late phase degradation subsequently observed. Quantitative analysis of boron carbide control rod degradation in FPT3 pointed to a need for improved modelling of chemical reactions involving this material, particularly its oxidation in steam; this has been studied in the BECARRE experiments conducted by IRSN in the International Source Term Programme, leading to better quantitative understanding and improved modelling in codes such as the European reference severe accident analysis code ASTEC. © 2012 Elsevier Ltd. All rights reserved.

Topics
  • stainless steel
  • silver
  • phase
  • experiment
  • carbide
  • Hydrogen
  • Boron
  • quantitative determination method
  • Indium
  • Cadmium
  • Actinide