Zobrazeno 1 - 10
of 1 378
pro vyhledávání: '"First wall"'
Publikováno v:
南方能源建设, Vol 11, Iss 3, Pp 75-80 (2024)
[Introduction] As a clean and efficient energy source, nuclear fusion promises to achieve global sustainable development in the future. For the first wall of Chinese helium-cooled solid breeder test blanket module, the temperature fields of helium, a
Externí odkaz:
https://doaj.org/article/db38b1df76434e78bd8c9b8ff9330274
Publikováno v:
He huaxue yu fangshe huaxue, Vol 46, Iss 2, Pp 125-130 (2024)
Helium-Cooled Ceramic Breeding Blanket Module(HCCB-TBM) will be installed on ITER machine to test its tritium breeding performance and thermal removal ability. The first wall of HCCB TBM is to handle the bombardment of plasma particles and confine th
Externí odkaz:
https://doaj.org/article/6e40b176e7f14ef1912d2358fd8df8ff
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
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101676- (2024)
The first wall (FW) of a blanket or divertor faces high temperature plasma. Thus, the FW needs to withstand extremely high heat fluxes. Periodic plasma pulses bring some reliability challenges to FW structures. The FW is composed of tiles, heat sink
Externí odkaz:
https://doaj.org/article/a8389344a9974505979d6e719d070faa
Autor:
Zhiyong Wang, Jianguo Ma, Zhihong Liu, Zhenfei Liu, Haoxiang Deng, Yudong Su, Nengtao Zhou, Hua Zhai, Jiefeng Wu
Publikováno v:
Journal of Materials Research and Technology, Vol 28, Iss , Pp 3514-3525 (2024)
As the core component of China Fusion Engineering Test Reactor (CFETR), the forming and manufacturing of the first wall faces severe challenges due to the constraints of materials, service environment and geometric structure. The microstructure and m
Externí odkaz:
https://doaj.org/article/3f7ba890d59b47c9b3334d2dc93a6729
Autor:
Renjith Ramachandran, S. Balaji
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101560- (2023)
Tungsten has been considered as a potential candidate material for the application of plasma-facing components in magnetic confinement fusion reactors. Fusion neutrons introduce severe displacement damage into the first-wall materials along with a hi
Externí odkaz:
https://doaj.org/article/13523b7d1cc041529a0d39a7b2731176
Processing and Properties of Sintered W/Steel Composites for the First Wall of Future Fusion Reactor
Autor:
Vishnu Ganesh, Daniel Dorow-Gerspach, Martin Bram, Jan Willem Coenen, Marius Wirtz, Gerald Pintsuk, Werner Theisen, Christian Linsmeier
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 1, Pp 177-192 (2023)
Functionally graded tungsten/steel composites are attractive to be used as an interlayer to join tungsten (W) and steel for the first wall of future fusion reactor to reduce the thermally induced stresses arising from the different coefficient of the
Externí odkaz:
https://doaj.org/article/0cef6072786c4b59913174d04b48e7ed
A Deep Learning-Based Method to Detect Hot-Spots in the Visible Video Diagnostics of Wendelstein 7-X
Autor:
Máté Szűcs, Tamás Szepesi, Christoph Biedermann, Gábor Cseh, Marcin Jakubowski, Gábor Kocsis, Ralf König, Marco Krause, Aleix Puig Sitjes, the W7-X Team
Publikováno v:
Journal of Nuclear Engineering, Vol 3, Iss 4, Pp 473-479 (2022)
Wendelstein 7-X (W7-X) is currently the largest optimized stellarator in operation in the world. Its main objective is to demonstrate long pulse operation and to investigate the suitability of this type of fusion device for a power plant. Maintaining
Externí odkaz:
https://doaj.org/article/45a29ba801b44db097dbb28a05d9eff5
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101431- (2023)
To study the manufacturing method of the tungsten armored first wall of tokamak devices, the W-316 L steel (W-SS) composite coatings were fabricated on 316 L steel substrates by detonation spraying (DS) as the interlayer of pure tungsten coatings man
Externí odkaz:
https://doaj.org/article/1624dd77d3d1458ca6c9f901842d929b
Autor:
Heiko Neuberger, Francisco Hernandez, Michael Rieth, Carsten Bonnekoh, Ludek Stratil, Ivo Dlouhy, Petr Dymacek, Oliver Müller, Lucas Adler, Ulrich Kunert
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101427- (2023)
At the KIT a hybrid manufacturing concept for nuclear fusion First Walls is developed combining aspects of conventional and Additive Manufacturing (AM) technologies. The state of the art for ITER does not cover all specifications of a DEMO relevant F
Externí odkaz:
https://doaj.org/article/5fbde9ffa9af46b6a60e31044746a50d