Zobrazeno 1 - 10
of 128
pro vyhledávání: '"Andrey Litnovsky"'
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
Publikováno v:
Metals, Vol 13, Iss 3, p 531 (2023)
Tungsten is foreseen presently as the plasma-facing material for divertors in fusion power plants. In order to achieve durable operation of divertors of current fusion reactors, an efficient way of maintaining the divertor functionality is needed. A
Externí odkaz:
https://doaj.org/article/129baafb475a46c385303416c2110836
Autor:
Huijuan Zhu, Xiaoyue Tan, Qingbo Tu, Yiran Mao, Zelin Shu, Jie Chen, Laima Luo, Andrey Litnovsky, Jan Willem Coenen, Christian Linsmeier, Yucheng Wu
Publikováno v:
Metals, Vol 12, Iss 9, p 1437 (2022)
During the spark plasma sintering (SPS) consolidation process, the pressure affects the densification and microstructure evolution of the sintered body. In this paper, the W-Cr-Y-Zr alloy powder was heated to 1000 °C under different applied pressure
Externí odkaz:
https://doaj.org/article/9c973bf45e984cbc80f114189a749b2e
Autor:
Andrey Litnovsky, Felix Klein, Xiaoyue Tan, Janina Ertmer, Jan W. Coenen, Christian Linsmeier, Jesus Gonzalez-Julian, Martin Bram, Ivan Povstugar, Thomas Morgan, Yury M. Gasparyan, Alexey Suchkov, Diana Bachurina, Duc Nguyen-Manh, Mark Gilbert, Damian Sobieraj, Jan S. Wróbel, Elena Tejado, Jiri Matejicek, Henning Zoz, Hans Ulrich Benz, Pawel Bittner, Anicha Reuban
Publikováno v:
Metals, Vol 11, Iss 8, p 1255 (2021)
Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials for the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine suppressed
Externí odkaz:
https://doaj.org/article/698e6e8b4ba347ddb9b7e7e9d3e623c6
Autor:
Xiaoyue Tan, Wujie Wang, Xiang Chen, Yiran Mao, Andrey Litnovsky, Felix Klein, Pawel Bittner, Jan Willem Coenen, Christian Linsmeier, Jiaqin Liu, Laima Luo, Yucheng Wu
Publikováno v:
Metals, Vol 11, Iss 6, p 886 (2021)
The tungsten (W) foil laminate is an advanced material concept developed as a solution for the low temperature brittleness of W. However, the deformed W foils inevitably undergo microstructure deterioration (crystallization) during the joining proces
Externí odkaz:
https://doaj.org/article/442c2851db124c8c900a3dbe1897e5df
Autor:
Damian Sobieraj, Jan S. Wróbel, Mark R. Gilbert, Andrey Litnovsky, Felix Klein, Krzysztof J. Kurzydłowski, Duc Nguyen-Manh
Publikováno v:
Metals, Vol 11, Iss 5, p 743 (2021)
W-Cr-Y smart alloys are potential material candidates for plasma facing components due to their protective behaviour during the loss-of-coolant accident (LOCA), while maintaining beneficial properties of W during the normal operation of the fusion po
Externí odkaz:
https://doaj.org/article/58a17c99080442dd99520160773381ad
Autor:
Maren Hellwig, Martin Köppen, Albert Hiller, Hans Rudolf Koslowski, Andrey Litnovsky, Klaus Schmid, Christian Schwab, Roger A. De Souza
Publikováno v:
Condensed Matter, Vol 4, Iss 1, p 29 (2019)
The effect of surface roughness on angular distributions of reflected and physically sputtered particles is investigated by ultra-high vacuum (UHV) ion-surface interaction experiments. For this purpose, a smooth (R a = 5.9 nm) and a rough (R a = 20.5
Externí odkaz:
https://doaj.org/article/3e40fbcb042644098b6f8be5d2c8c7e3
On Oxidation Resistance Mechanisms at 1273 K of Tungsten-Based Alloys Containing Chromium and Yttria
Autor:
Felix Klein, Tobias Wegener, Andrey Litnovsky, Marcin Rasinski, Xiaoyue Tan, Janina Schmitz, Christian Linsmeier, Jan Willem Coenen, Hongchu Du, Joachim Mayer, Uwe Breuer
Publikováno v:
Metals, Vol 8, Iss 7, p 488 (2018)
Tungsten (W) is currently deemed the main candidate for the plasma-facing armor material of the first wall of future fusion reactors, such as DEMO. Advantages of W include a high melting point, high thermal conductivity, low tritium retention, and lo
Externí odkaz:
https://doaj.org/article/a39f15e5ff964dc3acb98d3297295f32
Autor:
Andrey Litnovsky, Christian Linsmeier, Yucheng Wu, Martin Bram, Diana Bachurina, A. N. Suchkov, Jesus Gonzalez-Julian, J.W. Coenen, J. Schmitz, Xiaoyue Tan, F. Klein
Publikováno v:
Tungsten
Tungsten 3, 101–115 (2021). doi:10.1007/s42864-021-00079-5
Tungsten 3, 101–115 (2021). doi:10.1007/s42864-021-00079-5
Self-passivating, so-called smart alloys are under development for a future fusion power plant. These alloys containing tungsten, chromium and yttrium must possess an acceptable plasma performance during a regular plasma operation of a power plant an
Autor:
Hong-Yu Chen, J.W. Coenen, Liu Junwu, Weihua Wang, Xiaoyue Tan, X.Y. Zhu, Yucheng Wu, Lai-Ma Luo, Andrey Litnovsky, Xiang Ying Chen, Ch. Linsmeier, M. Wu, Yiran Mao
Publikováno v:
Powder Technology. 370:9-18
In this work, W-Cr-Zr as a self-passivating tungsten alloy is studied. Spark plasma sintering (SPS) is used to prepare the sample. The influence of the heating rate on the densification process and microstructure evolution during SPS was investigated