Zobrazeno 1 - 10
of 40
pro vyhledávání: '"M. Billone"'
Akademický článek
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Autor:
P. March, V. Elbaz, M. Billone, M.P. Puls, C. Getrey, D. Drouan, M. Philippe, Jean Desquines, S. Fourgeaud
Publikováno v:
Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2014, 453 (1-3), pp.131-150. ⟨10.1016/j.jnucmat.2014.06.049⟩
Journal of Nuclear Materials, Elsevier, 2014, 453 (1-3), pp.131-150. ⟨10.1016/j.jnucmat.2014.06.049⟩
International audience; Radial hydride precipitation in stress relieved Zircaloy-4 fuel claddings is studied using a new thermal–mechanical test. Two maximum temperatures for radial hydride precipitation heat treatment are studied, 350 and 450 °C
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d488554df104ebbacb7c79c2aa24f725
https://hal.archives-ouvertes.fr/hal-02641725
https://hal.archives-ouvertes.fr/hal-02641725
Autor:
M Billone
Publikováno v:
Fusion Engineering and Design. 27:179-190
Autor:
W. Daenner, M. Billone, D. Smith, D. Lorenzetto, A.R. Raffray, T. Kuroda, G. Shatalov, H. Yoshida, S. Mori, Y. Gohar, H. Takatsu, A. Siderov, K. Maki, A. Anitipenkov, G. Simbolotti, C. Baker, I. Sviatoslavsky
Publikováno v:
Fusion Technology. 19:1424-1431
The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical. A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based
The effect of fuel burnup on the embrittlement of various cladding alloys was examined with laboratory tests conducted under conditions relevant to loss-of-coolant accidents (LOCAs). The cladding materials tested were Zircaloy-4, Zircaloy-2, ZIRLO, M
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e8da9e1a95987751482091c796a3284
https://doi.org/10.2172/946677
https://doi.org/10.2172/946677
Akademický článek
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Publikováno v:
The Journal of the Acoustical Society of America. 55:1252-1258
A mathematical model of the human cochlear partition is developed to investigate the partition's stiffness. To date, no experiment has been performed on the partition to determine the difference between the dynamic and the statically measured stiffne
Autor:
Mark S. Tillack, G. Orient, M. Billone, K. Taghavi, G. E. Bell, P. Gierszewski, J. Garner, K. Shin, James Blanchard, Mohamed A. Abdou, H. Madarame
Publikováno v:
Fusion Technology. 8:1100-1108
For integrated testing of fusion nuclear components, it is likely that the test device parameters will not match the device parameters of a full scale fusion reactor because of cost constraints. This will result in changes in the behavior of the test