Výsledky vyhledávání

Effect of grain boundary planes on radiation-induced segregation (RIS) at near Σ3 grain boundaries in Fe-Cr alloy under ion irradiation

Autor: Q. Barrès, O. Tissot, E. Meslin, I. Mouton, B. Arnal, M. Loyer-Prost, C. Pareige

Publikováno v: Materials Characterization
Materials Characterization, 2022, 184, pp.111676. ⟨10.1016/j.matchar.2021.111676⟩

International audience; Ferritic Martensitic and ODS steels are widely studied for applications in the next generation of nuclear reactor. Their good mechanical properties and corrosion resistance make them good candidates. Under irradiation flux, mi

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6638c9e59b6d98ac582a4aa02b4438e4
https://cea.hal.science/cea-03540781/file/effet_plan_sigma3_versionfinale.pdf

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Akademický článek

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Akademický článek

Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.

Modeling and experimental study of long term creep damage in austenitic stainless steels

Autor: M. Blat-Yrieix, Y. Cui, C. Caes, B. Arnal, M. Sauzay, S. Dubiez-Legoff, C. Cabet, P. Bonnaillie

Publikováno v: Engineering Failure Analysis. 58:452-464

One of the main challenges for some reactors components in austenitic stainless steels at high temperature in-service conditions is the demonstration of their behavior up to 60 years. The creep lifetimes of these stainless steels require on the one h

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0d9e23a87316882f6f1887c8292d69bd
https://doi.org/10.1016/j.engfailanal.2015.08.009

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HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface

Autor: A. Wu, Jean-Christophe Brachet, J. Ribis, B. Arnal, E. Clouet, F. Leprêtre, E. Bordas

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2018, 504, pp.289-299. ⟨10.1016/j.jnucmat.2018.01.029⟩
Journal of Nuclear Materials, 2018, 504, pp.289-299. ⟨10.1016/j.jnucmat.2018.01.029⟩

International audience; Chromium-coated zirconium alloys are being studied as Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors (LWRs). Those materials are especially studied to improve the oxidation resistance of LWRs current fuel cl

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::550ba30647520d5dd191589256e906b1
https://hal-cea.archives-ouvertes.fr/cea-02428719/file/1-s2.0-S0022311517313338-main.pdf

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Atomic-scale Interface structure of a Cr-coated Zircaloy-4 material

Autor: J. Ribis, Jean-Christophe Brachet, B. Arnal, A. Wu, F. Barcelo

Publikováno v: Journal of Materials Science
Journal of Materials Science, 2018, 53, ⟨10.1007/s10853-018-2333-1⟩
Journal of Materials Science, Springer Verlag, 2018, 53, ⟨10.1007/s10853-018-2333-1⟩

International audience; Highly adherent, thin Cr coatings on Zr-based nuclear fuel claddings can be potentially used for the development of accident-tolerant fuels in light water reactors. To guarantee the successful implementation of Cr-coated Zr al

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::79c20e832596292932797d888d933d43
https://cea.hal.science/cea-02415674

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Assessing depression, anxiety and couple psychological well-being in pregnancy: a preliminary study

Autor: Carmen Moreno-Rosset, Isabel Ramírez-Uclés, Rosario Antequera-Jurado, B. Arnal-Remón

Publikováno v: Journal of Reproductive and Infant Psychology. 33:128-139

Objective: The aim of the study was to evaluate symptoms of depression and anxiety and psychological well-being in men and women in their third trimester of pregnancy, and to compare them with two control groups of men and non-pregnant women, both wi

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d850ba6fa055b515ba4300e572ca97b5
https://doi.org/10.1080/02646838.2014.986648

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Nano-size metallic oxide particle synthesis in Fe-Cr alloys by ion implantation

Autor: A. Gentils, J. Ribis, Ce Zheng, Vladimir A. Borodin, L. Delauche, B. Arnal

Publikováno v: Nucl.Instrum.Meth.B
Nucl.Instrum.Meth.B, 2017, 409, pp.333-337. ⟨10.1016/j.nimb.2017.03.067⟩
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Elsevier, 2017, 409, pp.333-337. ⟨10.1016/j.nimb.2017.03.067⟩
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2017, 409, pp.333-337. ⟨10.1016/j.nimb.2017.03.067⟩

International audience; Oxide Dispersion Strengthened (ODS) steels reinforced with metal oxide nanoparticles are advanced structural materials for nuclear and thermonuclear reactors. The understanding of the mechanisms involved in the precipitation o

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2dab2d12f8b8b4c91fb97886a8125719
https://hal.archives-ouvertes.fr/hal-01645630

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Thermal annealing behavior of nano-size metal-oxide particles synthesized by ion implantation in Fe-Cr alloy

Autor: Marion Descoins, Dominique Mangelinck, Vladimir A. Borodin, L. Delauche, A. Gentils, Ce Zheng, F. Dalle, J. Ribis, B. Arnal

Publikováno v: J.Appl.Phys.
J.Appl.Phys., 2017, 121 (17), pp.174305. ⟨10.1063/1.4982756⟩
Journal of Applied Physics
Journal of Applied Physics, 2017, 121 (17), pp.174305. ⟨10.1063/1.4982756⟩

International audience; Oxide dispersion strengthened (ODS) steels are promising structural materials for the next generation nuclear reactors, as well as fusion facilities. The detailed understanding of the mechanisms involved in the precipitation o

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3379864bb5f4488cf590d97edee1bd61
https://hal.archives-ouvertes.fr/hal-01582468

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