Zobrazeno 1 - 10
of 21
pro vyhledávání: '"C. Bernaudat"'
Publikováno v:
Revue Générale Nucléaire. :74-81
This paper describes a new approach to define an analytical fuel rod cladding failure criterion during fast power transients such as reactivity initiated accidents (RIAs). Though cladding failure is not a safety issue in itself in such situations, a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::266f3c10f3c9b26344ce4f252fae65bc
https://doi.org/10.1051/rgn/20102074
https://doi.org/10.1051/rgn/20102074
Autor:
Vincent Georgenthum, C. Bernaudat
Publikováno v:
La thermomécanique du crayon combustible.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::49dbb8febff2e9d127412b7d5e327d49
https://doi.org/10.1051/jtsfen/2013lat05
https://doi.org/10.1051/jtsfen/2013lat05
Autor:
C. Bernaudat
Publikováno v:
Nuclear Engineering and Design. 156:373-381
The mechanical behaviour of fractured nuclear fuel pellets is far from simple. In order to take correctly into account this behaviour and model it in the frame of a computer code, a lot of phenomena must be examined. Most of them can hardly be assess
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9812806d722c6ba409b10a3e1d81c7b0
https://doi.org/10.1016/0029-5493(94)00962-x
https://doi.org/10.1016/0029-5493(94)00962-x
Akademický článek
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Autor:
Jean Desquines, Yann Monerie, X. Averty, B. Cazalis, Pascal Yvon, C. Bernaudat, C. Poussard, M. Petit
Publikováno v:
Nuclear Technology
Nuclear Technology, American Nuclear Society, 2007, 157 (3), pp.215-229. ⟨10.13182/NT07-A3814⟩
Nuclear Technology, 2007, 157 (3), pp.215-229. ⟨10.13182/NT07-A3814⟩
Nuclear Technology, American Nuclear Society, 2007, 157 (3), pp.215-229. ⟨10.13182/NT07-A3814⟩
Nuclear Technology, 2007, 157 (3), pp.215-229. ⟨10.13182/NT07-A3814⟩
International audience; An assessment of the mechanical properties of the highly irradiated fuel claddings under high strain rate has been carried out in the framework of the PROMETRA program undertaken by the French Institut de Radioprotection et de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::12661b051c04017fdcc59dfe5bc95d79
https://hal.archives-ouvertes.fr/hal-03143868
https://hal.archives-ouvertes.fr/hal-03143868
Autor:
S. W. Dean, P. Yvon, C. Duguay, P. Bouffioux, A. Maurice, F. Rozenblum, P. Barberis, Jean-Marc Cloué, K. Audic, V. Chabretou, S. Carassou, B. Levasseur, C. Bernaudat
Publikováno v:
Journal of ASTM International. 7:103065
A stress relaxation on bent-beam specimen irradiation campaign was performed in the French material testing reactor OSIRIS in order to screen different materials according to their in-flux behavior and to derive constitutive laws that are used to des
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::649913c0f72f50bda0e604cac0a20d37
https://doi.org/10.1520/jai103065
https://doi.org/10.1520/jai103065
Akademický článek
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