Zobrazeno 1 - 10
of 1 700
pro vyhledávání: '"plasma facing components"'
Autor:
Federico Pesamosca, Timo Ravensbergen, Richard A. Pitts, Domenico Frattolillo, Mattia Erroi, Quentin Deliege, Peter C. de Vries, Luca Zabeo, Luigi Pangione, Ivo S. Carvalho, Anna Vu
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101781- (2024)
Real-time monitoring and control of thermal loads on tungsten plasma-facing components is mandatory for ITER to avoid their overheating during plasma discharges. For the Start of Research Operations (SRO) phase, dedicated First Wall Heat Load Control
Externí odkaz:
https://doaj.org/article/325f068298784394be89736f8a7f30d2
Autor:
Tao Huang, Qiuyue Nie, Tao Jiang, Cheng Chen, Yang Liu, Jinming Gao, Laizhong Cai, Xu Zhao, Xiaogang Wang
Publikováno v:
Frontiers in Physics, Vol 12 (2024)
As a high heat flux linear plasma device designed for studying divertor materials in future fusion reactors, HIT-PSI(Plasma Surface Interaction device at Harbin Institute of Technology) has been successfully constructed and has maintained stable oper
Externí odkaz:
https://doaj.org/article/a571b1279eb14bb9be10391dc1b2f34a
Measurement of velocity and diameter of tungsten particles produced by arcing using high-speed video
Autor:
Alberto Castillo Castillo, Martin Balden, Volker Rohde, Michael Laux, Peter Siemroth, Heinz Pursch, Juergen Sachtleben, Rudolf Neu
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101725- (2024)
Arcing is a mechanism of dust production and erosion in fusion devices. The masses and velocities of tungsten (W) particles produced by arcing is of special interest given that W is used as wall material in current experimental devices and is planned
Externí odkaz:
https://doaj.org/article/2b40d03bbe4e4569966f5f2e7841cd88
Akademický článek
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Autor:
J. Riesch, A. von Müller, Y. Mao, J.W. Coenen, B. Böswirth, S. Elgeti, M. Fuhr, H. Greuner, T. Höschen, K. Hunger, P. Junghanns, A. Lau, S. Roccella, L. Vanlitsenburgh, J.-H. You, Ch. Linsmeier, R. Neu
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101591- (2024)
Currently, tungsten fibre-reinforced (Wf) composites are regarded as promising materials for plasma-facing components of future magnetic confinement fusion devices. In this context, tungsten fibre-reinforced tungsten (Wf/W) is being investigated as a
Externí odkaz:
https://doaj.org/article/a99086a676db451493030f351b11f479
Autor:
Q. Tichit, A. Durif, J. Gaspar, Y. Anquetin, Y. Corre, M. Diez, L. Dubus, M. Firdaouss, J. Gerardin, A. Grosjean, J.P. Gunn, K. Krieger, M. Missirlian, S. Ratynskaia, P. Reilhac, M. Richou, F. Rigollet
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101537- (2023)
The consequences of tungsten (W) damaging processes, such as cracking and melting, on divertor lifetime and plasma operation are high priority issues for ITER. A sustained melting experiment was conducted in WEST using a 2 mm deep groove geometry on
Externí odkaz:
https://doaj.org/article/fd7599b33eb0402fbd322d8ecb4ff549
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101525- (2023)
Liquid lithium wettability has been investigated on novel zirconium-alloyed porous tungsten fabricated by the place-holder spark plasma sintering technique. This paper investigates the wetting properties of liquid lithium on the substrates by in vacu
Externí odkaz:
https://doaj.org/article/001c85e3c0aa4173b117b442620f0381
Autor:
Dirk Naujoks, Chandra-Prakash Dhard, Yuhe Feng, Yu Gao, Torsten Stange, Birger Buttenschön, Sergey A. Bozhenkov, Sebastijan Brezinsek, Kai Jakob Brunner, Gábor Cseh, Andreas Dinklage, David Ennis, Joris Fellinger, Eric Flom, Dorothea Gradic, Eduard Grigore, Dirk Hartmann, Frederik Henke, Marcin Jakubowski, Amit Kharwandikar, Mikhail Khokhlov, Jens Knauer, Gábor Kocsis, Petra Kornejew, Maciej Krychowiak, Matej Mayer, Paul McNeely, Daniel Medina, Rudolf Neu, Kian Rahbarnia, Cristian Ruset, Norbert Rust, Peter Scholz, Thomas Sieber, Ivan Stepanov, Naoki Tamura, Erhui Wang, Thomas Wegner, Daihong Zhang
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101514- (2023)
The transition to reactor-relevant materials for the plasma facing components (PFCs) is an important and necessary step to provide a proof of principle that the stellarator concept can meet the requirements of a future fusion reactor by demonstrating
Externí odkaz:
https://doaj.org/article/808cff5a3c344256a3be4e2785c080a9
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 1, Pp 193-203 (2023)
In this work we report the characterization of thin metallic coatings of interest for nuclear fusion technology through the ns double-pulse LIBS technique. The coatings, composed of a tungsten (W) or tungsten-tantalum (W-Ta) mixture were enriched wit
Externí odkaz:
https://doaj.org/article/b8333d9673e64bd3be12263e1afd822d
Autor:
Marianne Richou, Isabelle Chu, Geoffrey Darut, Raphael Maestracci, Manda Ramaniraka, Erick Meillot
Publikováno v:
Journal of Nuclear Engineering, Vol 3, Iss 4, Pp 453-460 (2022)
For the DEMO reactor, tungsten is considered as an armor material. Eurofer97 is planned to be used as a structural material for the first wall and in the divertor region, especially for the shielding liner component. To date, several joining solution
Externí odkaz:
https://doaj.org/article/360e0fa90d134e1ba38c998c4d77c456