Zobrazeno 1 - 10
of 72
pro vyhledávání: '"C. Amzallag"'
Autor:
J.-M. Martinez, Frederic Escourbiac, S. Panayotis, T. Hirai, V. Komarov, Mario Merola, C. Amzallag, V.R. Barabash, A. Durocher
Publikováno v:
Fusion Engineering and Design. 125:256-262
During the qualification program of the tungsten divertor vertical targets, the tested mock-ups (250 tested tungsten monoblocks in total) successfully demonstrate their thermal performances and structural integrity. However, some of the tested monobl
Autor:
I. Uytdenhouwen, Marius Wirtz, Jochen Linke, V.R. Barabash, A. Durocher, Mario Merola, T. Hirai, C. Amzallag, Gerald Pintsuk, Th. Loewenhoff, Frederic Escourbiac, S. Panayotis
Publikováno v:
Nuclear materials and energy 9, 616-622 (2016). doi:10.1016/j.nme.2016.07.003
Since the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R&D for high performance armor-heat sink joint were necessary to be implemented
Autor:
Gérard Degallaix, Francis Bouchet, N. Haddar, C. Amzallag, Suzanne Degallaix, V. Maillot, Antoine Fissolo, J. M. Stephan, J. C. Le Roux
Publikováno v:
Revue de Métallurgie. 101:1087-1099
Tests were performed on austenitic stainless steels. In order to investigate thermal fatigue resistance of quasi-structural specimens, test facilities enforcing temperature variations similar to those found under the operative conditions have been de
Publikováno v:
International Journal of Fatigue. 16:287-293
The rainflow procedure is a cycle-counting method that makes it possible to store service measurements in a form suitable for fatigue analysis of structures: fatigue life prediction and simulation testing. A consultation has been conducted by the aut
Publikováno v:
Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
This is a study of the 107 cycle fatigue limit of Type 304L Stainless Steel, as measured in fully reversed (R=-1) load-controlled tests, at 150°C and 300°C, in air and PWR water. The staircase method was used to determine the fatigue limit. The tes
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36b390ed52aa719b955c4de95826072b
https://doi.org/10.1007/978-3-319-48760-1_35
https://doi.org/10.1007/978-3-319-48760-1_35
Publikováno v:
Revue de Métallurgie. 90:697-708
We have studied the corrosion-fatigue crack initiation and propagation of different types of steels: two austenitic, one austenitic-ferritic, and one ferritic. The testing program had been established in order to define, particularly, the part in cor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::10ceb2a72d99ab4499d01811da4fe8c4
https://doi.org/10.1520/stp28717s
https://doi.org/10.1520/stp28717s