Zobrazeno 1 - 10
of 747
pro vyhledávání: '"Rasiński A"'
Autor:
Wu, Huace, Yi, Rongxing, Houben, Anne, Brezinsek, Sebastijan, Rasinski, Marcin, Li, Cong, Sergienko, Gennady, Liang, Yunfeng, Dittmar, Timo, Ding, Hongbin
Publikováno v:
In Nuclear Materials and Energy December 2024 41
Autor:
Tweer, Jannik, Day, Robin, Derra, Thomas, Dorow-Gerspach, Daniel, Gräfe, Stefan, Rasinski, Marcin, Wirtz, Marius, Linsmeier, Christian, Bergs, Thomas, Natour, Ghaleb
Publikováno v:
In Nuclear Materials and Energy December 2024 41
Autor:
Vuoriheimo, Tomi, Hakola, Antti, Likonen, Jari, Krieger, Karl, Balden, Martin, Bogdanović Radović, Iva, Provatas, Georgios, Siketić, Zdravko, Ivanković Nizić, Karla, Rasinski, Marcin, Brezinsek, Sebastijan
Publikováno v:
In Nuclear Materials and Energy December 2024 41
Autor:
Reuban, Anicha, Povstugar, Ivan, Rasiński, Marcin, Vayyala, Ashok, Litnovsky, Andrey, Coenen, Jan W., Linsmeier, Christian, Guillon, Olivier, Gonzalez-Julian, Jesus
Publikováno v:
In Corrosion Science 15 July 2024 235
Autor:
Do Duy, Khiem, Norizuki, Ryosuke, Fujiwara, Hikaru, Shirota, Kento, Tanaka, Teruya, Yagi, Juro, Rasinski, Marcin, Chikada, Takumi
Publikováno v:
In Journal of Nuclear Materials June 2024 594
Autor:
Jie Chen, Elena Tejado, Marcin Rasiński, Andrey Litnovsky, Duc Nguyen-Manh, Eric Prestat, Tamsin Whitfield, Jose Ygnacio Pastor, Martin Bram, Jan Willem Coenen, Christian Linsmeier, Jesus Gonzalez-Julian
Publikováno v:
Metals, Vol 14, Iss 9, p 1092 (2024)
The self-passivating yttrium-containing WCr alloy has been developed and researched as a potential plasma-facing armour material for fusion power plants. This study explores the use of yttria (Y2O3) powders instead of yttrium elemental powders in the
Externí odkaz:
https://doaj.org/article/8f12c0c9f9ea419eb9863bcdc8485029
Akademický článek
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Autor:
Tian, Chunhua, Ma, Yan, Ghafarollahi, Alireza, Patil, Piyush, Dehm, Gerhard, Bitzek, Erik, Rasinski, Marcin, Best, James P.
Publikováno v:
In Acta Materialia 15 October 2023 259
Autor:
M. Rasiński, S. Brezinsek, A. Kreter, T. Dittmar, K. Krieger, M. Balden, P. de Marne, R. Dux, M. Faitsch, A. Hakola, J. Likonen, E. Tsitrone, V. Rohde
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101539- (2023)
Tungsten (W) is the prime candidate for the plasma facing material in present and future fusion devices. When exposed to a plasma containing He ions, W can exhibit creation of sub-surface nano-bubbles leading to formation of nano-tendrils called fuzz
Externí odkaz:
https://doaj.org/article/4122f50747454304b47bda93c03655b8
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101518- (2023)
The estimation of the hydrogen isotope flux through a fusion reactor wall component is important for the material selection and in order to guarantee a safe and economical reactor operation. Since the permeation flux through a component cannot be mea
Externí odkaz:
https://doaj.org/article/174bfabfbdc14ae3bd16de00c532aa73