Zobrazeno 1 - 10
of 79
pro vyhledávání: '"C. Vorpahl"'
Autor:
F. Maviglia, M. Siccinio, C. Bachmann, W. Biel, M. Cavedon, E. Fable, G. Federici, M. Firdaouss, J. Gerardin, V. Hauer, I. Ivanova-Stanik, F. Janky, R. Kembleton, F. Militello, F. Subba, S. Varoutis, C. Vorpahl
Publikováno v:
Nuclear Materials and Energy, Vol 26, Iss , Pp 100897- (2021)
In the present work, the role of plasma facing components protection in driving the EU-DEMO design will be reviewed, focusing on steady-state and, especially, on transients. This work encompasses both the first wall (FW) as well as the divertor. In f
Externí odkaz:
https://doaj.org/article/fbb10fb9eac44709b448a6da619d65ce
Publikováno v:
Fusion Engineering and Design
In the current pre-concept phase of the European DEMO, integration studies of the systems in the Upper Port area are being carried out. In DEMO, the Upper Port of the Vacuum Vessel is extraordinarily large to allow for the vertical extraction of the
Autor:
C. Vorpahl, J. Gerardin, Irena Ivanova-Stanik, Wolfgang Biel, M. Cavedon, Stylianos Varoutis, Mattia Siccinio, M. Firdaouss, C. Bachmann, Volker Hauer, Francesco Maviglia, Fulvio Militello, R. Kembleton, E. Fable, Fabio Subba, G. Federici, F. Janky
Publikováno v:
Nuclear materials and energy 26, 100897-(2021). doi:10.1016/j.nme.2020.100897
Nuclear Materials and Energy
Nuclear materials and energy, 26, Art.-Nr. 100897
Nuclear Materials and Energy, Vol 26, Iss, Pp 100897-(2021)
Nuclear Materials and Energy
Nuclear materials and energy, 26, Art.-Nr. 100897
Nuclear Materials and Energy, Vol 26, Iss, Pp 100897-(2021)
In the present work, the role of plasma facing components protection in driving the EU-DEMO design will be reviewed, focusing on steady-state and, especially, on transients. This work encompasses both the first wall (FW) as well as the divertor. In f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b5a1335285d6e3724cca50d2b823e4fb
https://juser.fz-juelich.de/record/897406
https://juser.fz-juelich.de/record/897406
Autor:
A. Wilde, Francesco Maviglia, Z. Vizvary, Wayne Arter, P. Cooper, Th. Franke, M. Firdaouss, R. Gowland, E. V. Rosa Adame, T.R. Barrett, C. Bachmann, M. L. Richiusa, E. Flynn, C. Vorpahl, J. Gerardin, M. Kovari, Y. Xue, B. Chuilon
Publikováno v:
Fusion Engineering and Design
The anticipated heat flux limit of the European DEMO first wall is ∼1−2 MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than the steady state heat load and exceed the first wall limit, there
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d530ad9a30c82edcb66d68ee3d78b475
https://hdl.handle.net/21.11116/0000-0006-6CE3-121.11116/0000-0006-62F3-921.11116/0000-0006-62F5-7
https://hdl.handle.net/21.11116/0000-0006-6CE3-121.11116/0000-0006-62F3-921.11116/0000-0006-62F5-7
Autor:
Rafael Juarez, Victor Udintsev, N. Casal, Y. Ma, M. Kocan, Luciano Bertalot, José Luis Barbero, Michael Loughlin, B. Brichard, C. Vorpahl, Philip Andrew, H. Meister, T. Giacomin, V. Martin, M. Bassan, Robin Barnsley, A. Sirinelli, Frederic Le Guern, Michael Walsh, F. Mackel, Cristopher Watts, P. Maquet, Maarten De Bock, Pavel Shigin, Fabien Seyvet, Roger Reichle, George Vayakis
Publikováno v:
Fusion Engineering and Design
ITER will be the first fusion device able to maintain fusion for long periods of time and therefore suitable to test integrated technologies, materials, and physics regimes necessary for the commercial production of fusion-based electricity. Therefor
Autor:
Fabio Subba, C. Vorpahl, R. Hiwatari, Kazuo Hoshino, Satoshi Kakudate, Mattia Siccinio, Y. Someya, Jeong-Ha You, G. Federici, Yuki Homma, S. Suzuki, Nobuyuki Asakura, Hiroyasu Utoh, Yoshiteru Sakamoto
Publikováno v:
Nuclear Fusion
Concepts of the power exhaust and divertor design have been developed, with a high priority in the pre-conceptual design phase of the Japan–Europe broader approach DEMO design activity (BA DDA). Common critical issues are the large power exhaust an
Autor:
C. R. Seon, C. Vorpahl, A. G. Alekseev, Andrei Khodak, E.E. Mukhin, M. Smith, Takaki Hatae, E. Yatsuka, Jonathan Klabacha, S. Arshad, Alexander Zvonkov, S. Pak, Frederic Le Guern
Publikováno v:
Fusion Engineering and Design. 123:712-716
Numerous plasma-near mirrors of optical diagnostics in ITER require protection from erosion and deposition caused by impinging particles. This is achieved by 63 Diagnostic Shutters, which shall operate in vacuum under high thermal and neutron fluxes
Autor:
Francesco Maviglia, J. Keep, C. Vorpahl, Sergio Ciattaglia, R. Kembleton, A. Loving, G. Keech, Fabio Cismondi, C. Gliss, Th. Franke, C. Bachmann
Publikováno v:
Fusion Engineering and Design
Due to the limited irradiation lifetime of the structural material used for in-vessel components in DEMO, it will be necessary to replace all breeding blankets within the given planned maintenance window in order to meet DEMO availability targets (Ro
Publikováno v:
Fusion Engineering and Design
The DEMO blanket attachment concept is challenging due to several factors: the harsh radiation environment, the thermal expansion, the electro-magnetic loads, the remote maintenance feasibility, and the accurate control of the alignment of the breedi
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