Zobrazeno 1 - 10
of 170
pro vyhledávání: '"Reymond Matthieu"'
Publikováno v:
In Nuclear Engineering and Design October 2024 427
Autor:
Seo, Seokbin, Folsom, Charles, Jensen, Colby, Kamerman, David, Giaccardi, Luana, Cherubini, Marco, Suk, Pavel, Sevecek, Martin, Sercombe, Jerome, Guenot-Delahaie, Isabelle, Scolaro, Alessandro, Reymond, Matthieu, Kulacsy, Katalin, Herranz, Luis, Feria, Francisco, Aragón, Pau, Khvostov, Grigori, Khan, Imran, Deo, Anuj Kumar, Ravva, Srinivasa Rao, Calabrese, Rolando, Boldt, Felix, Sappl, Jonathan, Falk, Florian, Arkoma, Asko, Vincent, Georgenthum, Tasaki, Yudai, Kakiuchi, Kazuo, Udagawa, Yutaka, Delipei, Gregory, Cheron, Charles, Corson, James, Zhang, Jinzhao, Drieu, Thomas, Klouzal, Jan, Dostal, Martin, Matocha, Vitezslav, Kinkorová, Tereza, Fiorina, Carlo
Publikováno v:
In Nuclear Engineering and Design 15 December 2024 430
Autor:
Reymond, Matthieu, Doualle, Thomas, Sercombe, Jerome, Rocca, Mathilde, Nasselahsen, Mehdi, Colin, Christian, Pontillon, Yves, Gallais, Laurent
Publikováno v:
Journal of Applied Physics; 7/21/2023, Vol. 134 Issue 3, p1-13, 13p
Autor:
Doualle, Thomas1 thomas.doualle@cea.fr, Reymond, Matthieu1,2, Pontillon, Yves1, Gallais, Laurent2
Publikováno v:
EPJ Web of Conferences. 11/19/2021, Vol. 254, p1-5. 5p.
Akademický článek
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Autor:
Doualle Thomas, Le Guillous Vincent, Klosek Vincent, Onofri-Marroncle Claire, Reymond Matthieu, Gallais Laurent, Pontillon Yves
Publikováno v:
EPJ Web of Conferences, Vol 253, p 07005 (2021)
The knowledge of the thermal conductivity of nuclear fuel and its evolution as a function of temperature and burn up is a major challenge in the context of the evaluation and understanding of irradiated fuel performances in current reactors. It is al
Externí odkaz:
https://doaj.org/article/88d7f59f9fc1420f970681647e652a02
Publikováno v:
EPJ Web of Conferences, Vol 253, p 07004 (2021)
Linked to experimental data acquisition and to development of improved models, a better detailed description of the behaviour of the nuclear ceramics as regard to the fission gases release during thermal transient representative of nuclear accidents
Externí odkaz:
https://doaj.org/article/9d73bbd1dcf84e8ba394ec7ee9866e42
Autor:
de Montaigu, Amaury, Giakountis, Antonis, Rubin, Matthew, Tóth, Réka, Cremer, Frédéric, Sokolova, Vladislava, Porri, Aimone, Reymond, Matthieu, Weinig, Cynthia, Coupland, George
Publikováno v:
Proceedings of the National Academy of Sciences of the United States of America, 2015 Jan . 112(3), 905-910.
Externí odkaz:
https://www.jstor.org/stable/26459415
Autor:
Reymond, Matthieu
Publikováno v:
Physique [physics]. Ecole Centrale Marseille, 2022. Français. ⟨NNT : 2022ECDM0005⟩
In a Pressurized Water Reactor (PWR), the modeling of fuel behavior in accident situations such as Reactivity Initiated Accident (RIA) or Loss of Coolant Accident (LOCA) is necessary to predict the fuel behavior and to determine the safety criteria o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=od______3430::cb497af90ebdd5a998711962c65d2dec
https://theses.hal.science/tel-04012266
https://theses.hal.science/tel-04012266
Publikováno v:
Matériaux 2022
Matériaux 2022, 2022, Lille, France
Matériaux 2022, 2022, Lille, France
International audience
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::2695994b3d178939d464015cd8324168
https://hal.science/hal-03917313
https://hal.science/hal-03917313