Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Jean-Philippe Vernot"'
Publikováno v:
Journal of Physics D: Applied Physics
Journal of Physics D: Applied Physics, IOP Publishing, 2006, 39, pp.3193-3199. ⟨10.1088/0022-3727/39/15/S09⟩
Journal of Physics D: Applied Physics, IOP Publishing, 2006, 39, pp.3193-3199. ⟨10.1088/0022-3727/39/15/S09⟩
International audience; Specific wear of Rod Cluster Control Assemblies (RCCA) in Pressurized Water nuclear Reactors (PWR) results from contacts with their guides due to flow induced vibration. Particular sliding impact contact conditions and specifi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::77d98b0cdfbd15cc7acf187912cd4a37
https://doi.org/10.1088/0022-3727/39/15/s09
https://doi.org/10.1088/0022-3727/39/15/s09
Autor:
André Tonck, Jean-Philippe Vernot, Damien Kaczorowski, J. M. Georges, Sandrine Bec, André Bernard Vannes
Publikováno v:
Comptes Rendus de l'Académie des Sciences - Series IV - Physics. 2:739-747
The wear behaviour of an austenitic stainless steel is analysed using a tribometer working in pressurised high temperature water (PHTW). The precise contact conditions, low pressure impact and sliding contacts, play an important role on the surface w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8ea85fd83526c6cdaa65095cafcd30c2
https://doi.org/10.1016/s1296-2147(01)01216-1
https://doi.org/10.1016/s1296-2147(01)01216-1
Publikováno v:
ASME 2010 Pressure Vessels and Piping Conference: Volume 1.
NUREG report CR-6909 [1] proposed in 2007 new rules for evaluating environmental effects in fatigue analyses of new reactors components. These new rules, based on simple correlations, consider that Fen penalty factors (ratio of fatigue life in air at
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c7038d685dcb7a742480eb4ea7dff155
https://doi.org/10.1115/pvp2010-26027
https://doi.org/10.1115/pvp2010-26027
Publikováno v:
Volume 3: Design and Analysis.
In February/March 2007, The NRC issued Regulatory Guide “RG1.207” and Argonne National Laboratory issued NUREG/CR-6909 that is now applicable in the US for evaluations of PWR environmental effects in fatigue analyses of new reactor components. In
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::38f2950d970c2bebf016e80608eddb86
https://doi.org/10.1115/pvp2009-78129
https://doi.org/10.1115/pvp2009-78129
Publikováno v:
Volume 3: Design and Analysis.
During mid 2006, ANL issued a NUREG/CR-6909 [2] report that is now applicable in The US for evaluations of PWR environmental effects in the fatigue analysis of new reactor components. In order to assess the conservativeness of the application of this
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::46d04f5a56e4e7b9c881dc3cff964bad
https://doi.org/10.1115/pvp2008-61894
https://doi.org/10.1115/pvp2008-61894
Autor:
André Tonck, J. M. Georges, Jean-Philippe Vernot, Damien Kaczorowski, Sandrine Bec, André Bernard Vannes
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 4.
In nuclear power plants, slender tubular components are subjected to vibrations in a PHTW environment. As a result, the two contacting surfaces, tubes and their guides undergo impact at low contact pressures [1]. The components are usually made of st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5d697a41ec9944af3961c1a7948c13e
https://doi.org/10.1115/icone10-22699
https://doi.org/10.1115/icone10-22699