Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Yann Kayser"'
Autor:
Tobias Bolinder, Jacques Besson, Yann Kayser, Szabolcs Szavai, Patrick Le Delliou, Tomas Nicak, Dominique Moinereau, Anna Dahl, Levente Tatar, Kim Wallin, Stéphane Marie, Marta Serrano
Publikováno v:
Volume 6A: Materials and Fabrication
Moinereau, D, Le Delliou, P, Dahl, A, Kayser, Y, Szavai, S, Tatar, L, Bolinder, T, Serrano, M, Besson, J, Nicak, T, Wallin, K & Marie, S 2018, The experimental work in support to ATLAS+ project . in ASME 2018 Pressure Vessels and Piping Conference : Materials and Fabrication . vol. 6A, PVP2018-84697, American Society of Mechanical Engineers (ASME), ASME 2018 Pressure Vessels and Piping Conference, PVP2018, Prague, Czech Republic, 15/07/18 . https://doi.org/10.1115/PVP2018-84697
Moinereau, D, Le Delliou, P, Dahl, A, Kayser, Y, Szavai, S, Tatar, L, Bolinder, T, Serrano, M, Besson, J, Nicak, T, Wallin, K & Marie, S 2018, The experimental work in support to ATLAS+ project . in ASME 2018 Pressure Vessels and Piping Conference : Materials and Fabrication . vol. 6A, PVP2018-84697, American Society of Mechanical Engineers (ASME), ASME 2018 Pressure Vessels and Piping Conference, PVP2018, Prague, Czech Republic, 15/07/18 . https://doi.org/10.1115/PVP2018-84697
The 4-years European project ATLAS+ project was launched in June 2017. Its main objective is to develop advanced structural assessment tools to address the remaining technology gaps for the safe and long term operation of nuclear reactor pressure coo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::128728a4a9e698d1e5778302fae2b00a
https://cris.vtt.fi/en/publications/ad3bc87e-444d-4de7-ab17-ba838b16604f
https://cris.vtt.fi/en/publications/ad3bc87e-444d-4de7-ab17-ba838b16604f
Autor:
B. Drubay, M.H. Lacire, Bruno Barthelet, S. Marie, Yann Kayser, V. Rougier, C. Naudin, M. Triay, Stéphane Chapuliot, P. Le Delliou, P. Gilles
Publikováno v:
International Journal of Pressure Vessels and Piping. 84:601-613
French nuclear codes include flaw assessment procedures: the RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction rules for mechanical components of FBR nuclear islands and
Autor:
B. Drubay, M. Triay, P. Gilles, M.H. Lacire, Bruno Barthelet, Yann Kayser, V. Rougier, P. Le Delliou, Stéphane Chapuliot, S. Marie, C. Naudin
Publikováno v:
International Journal of Pressure Vessels and Piping. 84:590-600
Two French nuclear codes include flaw assessment procedures: the RSE-M code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction rules for mechanical components of FBR nuclear islands
Autor:
Stéphane Chapuliot, Bruno Barthelet, B. Drubay, S. Marie, M. Triay, C. Naudin, M.H. Lacire, P. Le Delliou, Yann Kayser, V. Rougier, P. Gilles
Publikováno v:
International Journal of Pressure Vessels and Piping. 84:687-696
French nuclear codes include flaw assessment procedures: the RSE-M Code “Rules for In-service Inspection of Nuclear Power Plant Components” and the RCC-MR code “Design and Construction Rules for Mechanical Components of FBR Nuclear Islands and
Autor:
Myriam Bourgeois, Sutham Arun, Yann Kayser, David J. Smith, Michael Smith, Son Do, Andrew H. Sherry
Publikováno v:
Volume 6A: Materials and Fabrication.
The STYLE EU Framework 7 project is examining the structural integrity of non-RPV components in reactor primary circuits. One of its focus areas is the impact of high magnitude weld residual stresses on the initiation and growth of cracks in austenit
Publikováno v:
Volume 6A: Materials and Fabrication.
Within the framework of European project STYLE [1], a fracture test on a pipe containing a through wall crack in a narrow gap Inconel Dissimilar Metals weld (welds named hereafter DMW) has been performed. The work is focusing on the Inconel - ferriti
Publikováno v:
Volume 1: Codes and Standards.
The fourth edition of the RCC-MR code was issued in French and English versions in October 2007 by AFCEN (Association Francaise pour les regles de Conception et de Construction des Materiels des Chaudieres Electro-nucleaires). In the frame of this ne
Publikováno v:
International Journal of Pressure Vessels and Piping
International Journal of Pressure Vessels and Piping, 2008, 85 (10), pp.681-693. ⟨10.1016/j.ijpvp.2008.02.009⟩
International Journal of Pressure Vessels and Piping, 2008, 85 (10), pp.681-693. ⟨10.1016/j.ijpvp.2008.02.009⟩
This paper presents recent modifications of the Leak Before Break procedure of the A16 appendix from French RCC-MR nuclear code and the improvements that will be proposed. The first part of the study deals with the prediction of the crack size at pen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::00be915b6a446f137179ea6a093a5dff
https://hal.archives-ouvertes.fr/hal-03005055
https://hal.archives-ouvertes.fr/hal-03005055
Publikováno v:
Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance.
The RSE-M Code provides rules and requirements for in-service inspection of French Pressurized Water Reactor power plants. The Code gives non mandatory guidance for analytical evaluation of flaws. Flaw assessment procedures rely on fracture mechanics
Publikováno v:
Volume 3: Design and Analysis.
RSE-M and RCC-MR codes provide flaw assessment methodologies and related tools for Nuclear Power Plant. AREVA, CEA and EDF developed in particular a large set of compendia for the calculation of the parameter J for various components (plates, pipes,