Výsledky vyhledávání - "Didier Hamon"

In-situ time-resolved study of structural evolutions in a zirconium alloy during high temperature oxidation and cooling

Autor: Raphaëlle Guillou, Caroline Toffolon-Masclet, D. Menut, Jean-Luc Béchade, M. Le Saux, Jean-Christophe Brachet, Didier Hamon, Dominique Thiaudière, Elodie Rouesne

Publikováno v: Materials Characterization
Materials Characterization, 2019, 158, ⟨10.1016/j.matchar.2019.109971⟩

International audience; In-situ time-resolved Synchrotron X-ray diffraction analyses were performed on zirconium alloy (Zircaloy-4) sheet samples, during their heating, isothermal oxidation at 700, 800 and 900 degrees C under a flowing mixture of He

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7f12f9bf470eaeb3642ae375b8869fc8
https://hal.science/hal-02431028/document

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Chemical interaction of Austenitic and Ferritic Steels with B4C Powder in Liquid Sodium at 600DC

Autor: Michel Tabarant, Fabien Rouillard, Didier Hamon, Marie Romedenne, Daniel Monceau

Publikováno v: Corrosion
Corrosion, 2018, 75 (10), pp.1173-1182. ⟨10.5006/3199⟩
Corrosion, National Association of Corrosion Engineers, 2018, 75 (10), pp.1173-1182. ⟨10.5006/3199⟩

In the framework of studies on the control rods’ lifetime for Sodium Fast Reactor, three commercial steels were exposed to B4C powder in liquid sodium at 600°C for durations up to 3,000 h. Analyses by optical and secondary electron microscopy, x-r

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::922e4a964eb7454fce31fa3aed35011a
https://cea.hal.science/cea-02339815/file/201800000555.pdf

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Carburization of austenitic and ferritic steels in carbon-saturated sodium: preliminary results on the diffusion coefficient of carbon at 873 K

Autor: Fabien Rouillard, Daniel Monceau, Brigitte Duprey, Didier Hamon, Marie Romedenne, Michel Tabarant

Publikováno v: Oxidation of Metals
Oxidation of Metals, Springer Verlag, 2017, vol. 87 (n° 5-6), pp. 643-653. ⟨10.1007/s11085-017-9733-5⟩
Oxidation of Metals, 2017, vol. 87 (n° 5-6), pp. 643-653. ⟨10.1007/s11085-017-9733-5⟩

International audience; Three commercial steels were exposed to carbon-saturated sodium at 873 K for durations up to 5000 h. Analyses by optical microscopy, infrared-inductive carbon combustion, electron probe microanalysis and glow discharge optical

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5367eea14765bac730706104498326ec
https://oatao.univ-toulouse.fr/18113/

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Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe

Autor: Caroline Raepsaet, Jean-Christophe Brachet, Jean-Luc Lacour, Frédéric Ott, Elodie Rouesne, Valérie Vandenberghe, Guy Bayon, Jean-Luc Béchade, Didier Hamon, Matthieu Le Saux, Stéphane Urvoy, Caroline Toffolon-Masclet

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, 2017, 488, pp.267-286. ⟨10.1016/j.jnucmat.2017.03.009⟩
Journal of Nuclear Materials, Elsevier, 2017, 488, pp.267-286. 〈http://www.sciencedirect.com/science/article/pii/S0022311516308960〉. 〈10.1016/j.jnucmat.2017.03.009〉
Journal of Nuclear Materials, Elsevier, 2017, 488, ⟨10.1016/j.jnucmat.2017.03.009⟩
Journal of Nuclear Materials, Elsevier, 2017, 488, pp.267-286. ⟨10.1016/j.jnucmat.2017.03.009⟩

International audience; This paper gives an overview of a multi-scale experimental study of the secondary hydriding phenomena that can occur in nuclear fuel cladding materials exposed to steam at high temperature (HT) after having burst (loss-of-cool

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::24ca8cbff68204ff1bf8ee7fd75995a3
https://cea.hal.science/cea-01488896

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Carburization of austenitic and ferritic stainless steels in liquid sodium: Comparison between experimental observations and simulations

Autor: Fabien Rouillard, Benoit Malard, Daniel Monceau, Marie Romedenne, Didier Hamon

Publikováno v: Corrosion Science
Corrosion Science, Elsevier, 2019, 159, pp.108147. ⟨10.1016/j.corsci.2019.108147⟩

International audience; Three steels were exposed in carburizing sodium at 600 and 650 °C. The kinetics and extent of carburization were characterized. Numerical simulations using the coupled thermodynamic-kinetic modeling software DICTRA were perfo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c5104350a3802ffe408378b71bc130c0
https://doi.org/10.1016/j.corsci.2019.108147

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Chemical and microstructural evolution on ODS Fe–14CrWTi steel during manufacturing stages

Autor: M.H. Mathon, Didier Hamon, Y. de Carlan, J. Malaplate, P. Olier, L. Chaffron, D. Nunes, L. Toualbi

Publikováno v: Journal of Nuclear Materials. 428:40-46

Oxide Dispersion Strengthened (ODS) steels are promising candidate materials for fission and fusion applications thanks to their improved properties related to both their fine grained microstructure and high density of Y–Ti–O nanoscale clusters (

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::93838bc09336a4a123819cbdb6844836
https://doi.org/10.1016/j.jnucmat.2011.10.042

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Oxygen, Hydrogen and Main Alloying Chemical Elements Partitioning Upon Alpha←→Beta Phase Transformation in Zirconium Alloys

Autor: Caroline Toffolon-Masclet, Julien Jourdan, Anthony Stern, T. Guilbert, Jean Christophe Brachet, Gwenaël Trego, Didier Hamon, Caroline Raepsaet

Publikováno v: Solid State Phenomena. :753-759

Due to their adequate properties, zirconium alloys are the reference materials for the nuclear fuel cladding tubes of Light Water Reactors (LWR). During some hypothetical accidental High Temperature (HT) transients, the materials should experience he

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3e93041f6cd0b52357d32352f1f33ce6
https://doi.org/10.4028/www.scientific.net/ssp.172-174.753

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Oxidation kinetics and oxygen diffusion in low-tin Zircaloy-4 up to 1523K

Autor: T. Guilbert, Didier Hamon, X. Ma, Caroline Toffolon-Masclet, Jean-Christophe Brachet

Publikováno v: Journal of Nuclear Energy
Journal of Nuclear Energy, Elsevier, 2008, 377, ⟨10.1016/j.jnucmat.2010.03.004⟩
Journal of Nuclear Energy, 2008, 377, ⟨10.1016/j.jnucmat.2010.03.004⟩

This paper deals with the study of oxidation kinetics and the identification of oxygen diffusion coefficients of low-tin Zy-4 alloy at intermediate (973 K ⩽ T ⩽ 1123 K) and high temperatures (T ⩾ 1373 K). Two different cases were considered: di

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7db5148cca4865e939570f1f2e36ce0c
https://doi.org/10.1016/j.jnucmat.2008.03.012

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Quantification and local distribution of hydrogen within Zircaloy-4 PWR nuclear fuel cladding tubes at the nuclear microprobe of the Pierre Süe Laboratory from μ-ERDA

Autor: Didier Hamon, Caroline Raepsaet, Jean-Christophe Brachet, Ph. Bossis, Jean-Luc Béchade

Publikováno v: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 266:2424-2428

Hydrogen content and its distribution in in-core materials of nuclear plants are known to have a strong influence on their behaviour, especially on their mechanical properties but also on their corrosion resistance. This point has to be largely inves

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d58187b5bfbf6a34eef93f223d89f6a9
https://doi.org/10.1016/j.nimb.2008.03.041

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Effect of the thermal ageing on the tensile and impact properties of a 18%Cr ODS ferritic steel

Autor: André Pineau, Jérôme Crépin, P. Wident, Veronique Garat, Mohamed Sennour, Serge Vincent, Anne Laure Rouffié, Didier Hamon, Benoit Tanguy, Benjamin Fournier

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2014, 445, pp.37-42. ⟨10.1016/j.jnucmat.2013.10.030⟩
Journal of Nuclear Materials, 2014, 445, pp.37-42. ⟨10.1016/j.jnucmat.2013.10.030⟩
Journal of Nuclear Materials, 2014, 445 (1-3), pp.37-42. ⟨10.1016/j.jnucmat.2013.10.030⟩

International audience; The effects of the thermal ageing at 400 °C, 500 °C and 600 °C during 5000 h on the mechanical properties of a 18%Cr ODS ferritic steel are investigated. A hardening effect is observed after ageing at 400 °C and 500 °C, p

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7f26a20ef54027c3fb03911a79ffd57b
https://hal-mines-paristech.archives-ouvertes.fr/hal-00926575

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