Výsledky vyhledávání - "Cédric Pokor"

Model of corrosion cracking of irradiated austenitic steels. Part 1. Analysis of damage mechanisms and formulation of the defining

Autor: Cédric Pokor, Aki Toivonen, Faiza Sefta

Publikováno v: Voprosy Materialovedeniya. :154-177

Mechanisms having a potential effect on irradiation assisted stress corrosion cracking (IASCC) of austenitic steels in the LWR environment have been analyzed. Based on the analysis and generalization of reference and original data on IASCC, an IASCC

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5b38d4250cc133937c5f38957b4983c1
https://doi.org/10.22349/1994-6716-2019-97-1-154-177

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Model of corrosion cracking of irradiated austenitic steels. Part 2. Determination of model parameters and its verification

Autor: B. Z. Margolin, A. A. Sorokin, N. E. Pirogova, V. A. Potapova, Aki Toivonen, Faiza Sefta, Cédric Pokor

Publikováno v: Voprosy Materialovedeniya. :178-190

Based on the analysis and generalization of reference and original experimental data unknown coefficients, parameters and functions in constitutive equations of the model developed in the first part of article have been defined. The model has been ve

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::611359132a5c1b4a7369659c3d7ff3f2
https://doi.org/10.22349/1994-6716-2019-98-2-178-190

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Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation

Autor: Cédric Pokor, N. E. Pirogova, Boris Margolin, Faiza Sefta, Aki Toivonen, A. A. Sorokin

Publikováno v: Margolin, B, Sorokin, A, Pirogova, N, Toivonen, A, Sefta, F & Pokor, C 2020, ' Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation ', Engineering Failure Analysis, vol. 107, 104235 . https://doi.org/10.1016/j.engfailanal.2019.104235

The austenitic steels used for RPV internals of light water reactors (LWR) are considered. Mechanisms having a potential effect on irradiation assisted stress corrosion cracking (IASCC) of austenitic steels in the LWR environment have been analyzed.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8c225800fbd0b300be7a8dce1aed704e
https://cris.vtt.fi/en/publications/f3946d6b-30c9-4ccc-8f9d-a75465a83b6f

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TEM and EFTEM characterization of solution annealed 304L stainless steel irradiated in PHENIX, up to 36dpa and at 390°C

Autor: Cédric Pokor, A. Renault, J. Malaplate, P. Gavoille

Publikováno v: Journal of Nuclear Materials. 421:124-131

Imaging of solution-annealed 304L stainless steel irradiated in the PHENIX reactor, up to a dose of 36 displacements per atom (dpa) and at a temperature of 390 °C was performed by using conventional transmission electron microscopy (TEM) and energy-

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::45cb3d699506dcacb0a60163386fd88c
https://doi.org/10.1016/j.jnucmat.2011.10.049

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Microstructural Evolution of Neutron Irradiated Stainless Steels

Autor: Marc Delnondedieu, Philippe Dubuisson, E. Keilova, Yannick Thebault, Dominique Loisnard, J. Kocik, Emmanuel Lemaire, Cédric Pokor, Jean-Paul Massoud, Nathalie Ligneau

Publikováno v: Revue Générale Nucléaire. :31-37

Materials of the core internals of Pressurized Water Reactors (austenitic stainless steels) are submitted to neutron irradiation. Some baffle/former bolt cracking were detected by non-destructive examinations and removed for metallurgical examination

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::0e1a2118f9b25007369bf3729d9e1679
https://doi.org/10.1051/rgn/20076031

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Correlation of radiation-induced changes in microstructure/microchemistry, density and thermo-electric power of type 304L and 316 stainless steels irradiated in the Phénix reactor

Autor: Alexandra Renault Laborne, Cédric Pokor, Benoit Tanguy, P. Gavoille, J. Malaplate

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2015, 460, pp.72-81. ⟨10.1016/j.jnucmat.2015.02.014⟩
Journal of Nuclear Materials, 2015, 460, pp.72-81. ⟨10.1016/j.jnucmat.2015.02.014⟩

Annealed specimens of type 304L and 316 stainless steel and cold-worked 316 specimens were irradiated in the Phenix reactor in the temperature range 381–394 °C and to different damage doses up to 39 dpa. The microstructure and microchemistry of bo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6c634f495cd31aabaa10de09ef28509f
https://hal-cea.archives-ouvertes.fr/cea-03200171

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Characterization of Precipitates in 316 Stainless Steel Neutron-Irradiated at ∼390°C by the Combination of CDF-TEM, EF-TEM, and HR-TEM

Autor: J. Malaplate, Alexandra Renault-Laborne, Cédric Pokor, Benoit Tanguy

Publikováno v: Effects of Radiation on Nuclear Materials: 26th Volume
Effects of Radiation on Nuclear Materials: 26th Volume, 1572, ASTM International, pp.74-97, 2014, 978-0-8031-7589-1. ⟨10.1520/STP157220130096⟩

26th Symposium on Effects of Radiation on Nuclear Materials. JUN 12-13, 2013. Indianapolis.; International audience; In this work, the combination of Conventional Dark Field (CDF), Energy Filtered (EF), and High Resolution (HR) Transmission Electron

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fc5db0f7e83100a36017e2f5fe5b68fb
https://cea.hal.science/cea-03585422

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