Study of the evolution of stresses and associated mechanisms in zirconia growing at high temperature on Zircaloy-4 by use of synchrotron radiation

Autor: Bouayoune, Adam, Guillou, R., Jean-Luc, Béchade, Rouesne, E., Grosseau-Poussard, Jean-Luc, Panicaud, B., Thiaudière, D., Le Saux, Matthieu

Publikováno v: Corrosion Science
Corrosion Science, 2023, 221, pp.111328. ⟨10.1016/j.corsci.2023.111328⟩

The present work studied the evolution of stresses and associated mechanisms, related to viscoplastic behavior during relaxation, in the zirconia layer formed during the oxidation of Zircaloy-4 under a He/O2 mixture, at temperatures of 700 °C, 800 �

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::c65fbca70032cfb161d311a4ad2d4e5d
https://ensta-bretagne.hal.science/hal-04161374

Predicting carbon diffusion in cementite from first principles

Autor: Thomas Schuler, Océane Buggenhoudt, Jean-Luc Béchade, Chu-Chun Fu

Publikováno v: Physical Review Materials
Physical Review Materials, American Physical Society, 2021, 5, pp.063401. ⟨10.1103/PhysRevMaterials.5.063401⟩
Physical Review Materials, 2021, 5, pp.063401. ⟨10.1103/PhysRevMaterials.5.063401⟩

Combining first-principles calculations with recently developed statistical physics tools, we determine carbon diffusion mechanisms and the resulting diffusion coefficients in pure-Fe and weakly alloyed ${M}_{3}\mathrm{C}$ cementites. The predicted c

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3d5c2ad1d4fa9ce26ef8670d205d6a0d
https://hal-cea.archives-ouvertes.fr/cea-03350631/document

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

Microstructure and mechanical properties relationship of additively manufactured 316L stainless steel by selective laser melting

Autor: Anne-Helene Puichaud, Pierre-François Giroux, Frédéric Schuster, Fernando Lomello, Aziz Chniouel, Jean-Luc Béchade, Elodie Rouesne, Hicham Maskrot, Camille Flament

Publikováno v: EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2019, 5, pp.23. ⟨10.1051/epjn/2019051⟩
EPJ Nuclear Sciences & Technologies, Vol 5, p 23 (2019)
EPJ N-Nuclear Sciences & Technologies, 2019, 5, pp.23. ⟨10.1051/epjn/2019051⟩

International audience; Additive manufacturing (AM) is rapidly expanding in many industrial applications because of the versatile possibilities of fast and complex fabrication of added value products. This manufacturing process would significantly re

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::55e617f6fdee1ae758e320665d82bb25
https://doi.org/10.1051/epjn/2019051

A polycrystalline modeling of the mechanical behavior of neutron irradiated zirconium alloys

Autor: Fabien Onimus, Jean-Luc Béchade

Publikováno v: Journal of Nuclear Materials. 384:163-174

Zirconium alloys used as fuel cladding tubes in the nuclear industry undergo important changes after neutron irradiation in the microstructure as well as in the mechanical properties. However, the effects of the specific post-irradiation deformation

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f5cfdd652e832ca26aec7d9d48686004
https://doi.org/10.1016/j.jnucmat.2008.11.006