Zobrazeno 1 - 10
of 145
pro vyhledávání: '"E Van Walle"'
Autor:
J. Martín, Diego Ferreño, I. Gorrochategui, Federico Gutiérrez-Solana, E. van Walle, Marc Scibetta, Roberto Lacalle
Publikováno v:
Journal of Nuclear Materials. 411:25-40
This work presents the results of the fracture characterisation of the weld material of a nuclear vessel, currently in service, in the ductile to brittle transition region. The tests consisted of Charpy impact and tensile tests, performed in the fram
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::683df7a96047c205bdca07fb4bb97ec8
https://doi.org/10.1016/j.jnucmat.2011.01.024
https://doi.org/10.1016/j.jnucmat.2011.01.024
Autor:
Masayuki Hasegawa, A. Almazouzi, Tadakatsu Ohkubo, E. van Walle, Yasuyoshi Nagai, Masahiko Hatakeyama, N. Tsuchiya, R. Gerard, Takeshi Toyama
Publikováno v:
Journal of Nuclear Materials. 405:177-180
Irradiation-induced changes of the atomic distributions of solute and impurity elements around carbides in a reactor pressure vessel steel of a Belgium nuclear power reactor were investigated by laser-assisted local electrode-type three-dimensional a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::64427b8d0477abd90c9729746fdaacce
https://doi.org/10.1016/j.jnucmat.2010.08.011
https://doi.org/10.1016/j.jnucmat.2010.08.011
Autor:
E. van Walle, Diego Ferreño, I. Gorrochategui, Roberto Lacalle, R. Cicero, Federico Gutiérrez-Solana, Marc Scibetta
Publikováno v:
Engineering Failure Analysis. 17:259-269
The structural integrity of a Spanish nuclear vessel was assessed by obtaining the operation pressure–temperature (P–T) limit curves relevant to the beltline region according to the ASME Code. This method requires the knowledge of the material fr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bff2f0fbb971571f1297cb84eedf4b85
https://doi.org/10.1016/j.engfailanal.2009.06.007
https://doi.org/10.1016/j.engfailanal.2009.06.007
Autor:
E. van Walle, Diego Ferreño, I. Gorrochategui, Roberto Lacalle, Federico Gutiérrez-Solana, Marc Scibetta
Publikováno v:
Engineering Fracture Mechanics. 76:2495-2511
In this work, a methodology based on the Master Curve approach and the reconstitution of specimens is validated and applied to the vessel base metal of the currently in service Spanish boiling water reactor of the Santa Maria de Garona nuclear power
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b4cfb9076df995e40213ebffae1156c1
https://doi.org/10.1016/j.engfracmech.2009.08.010
https://doi.org/10.1016/j.engfracmech.2009.08.010
Publikováno v:
Engineering Fracture Mechanics. 75:3599-3610
Experimental crack resistance curves obtained from miniature compact tension, MC(T), specimens were found to be significantly less tough than those obtained on standard one inch 1T-C(T) specimens. In order to investigate the fundamental reasons behin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b3042c2d29d0fb81911765615d45c67e
https://doi.org/10.1016/j.engfracmech.2007.05.008
https://doi.org/10.1016/j.engfracmech.2007.05.008
Autor:
Zilong Tang, E. van Walle, Masashi Hasegawa, Takeshi Toyama, A. Almazouzi, R. Gerard, Yasuyoshi Nagai
Publikováno v:
Acta Materialia. 55:6852-6860
The nanostructural evolution of irradiation-induced Cu-rich nanoprecipitates (CRNPs) and vacancy clusters in surveillance test specimens of in-service commercial nuclear reactor pressure vessel steel welds of Doel-1 and Doel-2 are revealed by combini
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6f775fd24368d053de1806344a0cc31
https://doi.org/10.1016/j.actamat.2007.08.047
https://doi.org/10.1016/j.actamat.2007.08.047
Publikováno v:
International Journal of Pressure Vessels and Piping. 84:536-544
In the context of existing regulatory codes, the integrity assessment of the pressure vessel of a nuclear power plant (NPP) is based on the empirical assumption that the fracture toughness of the surveillance materials, expressed in terms of a lower
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a3e04ae186a23bec7dc3544b1e7a2786
https://doi.org/10.1016/j.ijpvp.2007.05.001
https://doi.org/10.1016/j.ijpvp.2007.05.001
Publikováno v:
Journal of Nuclear Materials. 362:283-286
Tensile properties and internal friction of thermally aged (at 773 K) Fe–1 wt% Cu alloys are measured as a function of copper precipitation in the temperature region between 100 and 600 K. Two regimes have been clearly identified in terms of yield
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::41ae0c41ec804e7d869b96a6c48ffc05
https://doi.org/10.1016/j.jnucmat.2007.01.226
https://doi.org/10.1016/j.jnucmat.2007.01.226
Publikováno v:
Engineering Fracture Mechanics. 73:524-534
The normalization data reduction (NDR) technique is an analytical methodology for characterizing the upper shelf fracture toughness of steels in the ductile regime, both in terms of critical toughness (JIc) and resistance to ductile crack extension (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3e2c2635436799decf7d8eb0470c4f67
https://doi.org/10.1016/j.engfracmech.2005.08.009
https://doi.org/10.1016/j.engfracmech.2005.08.009
Publikováno v:
Strength of Materials. 36:19-32
Mechanical properties of WWER-440 RPV weld joints have been studied with account of different states of the material: baseline (unirradiated), irradiated up to the average fast neutron fluence of 6.5*10^19 n/cm^2, irradiated and eventually annealed,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::302495f4b6545e6552f5fba8d5a8af96
https://doi.org/10.1023/b:stom.0000020110.18433.d8
https://doi.org/10.1023/b:stom.0000020110.18433.d8