Zobrazeno 1 - 10
of 33
pro vyhledávání: '"F. Domptail"'
Autor:
J.H. You, E. Visca, T. Barrett, B. Böswirth, F. Crescenzi, F. Domptail, M. Fursdon, F. Gallay, B-E. Ghidersa, H. Greuner, M. Li, A.v. Müller, J. Reiser, M. Richou, S. Roccella, Ch. Vorpahl
Publikováno v:
Nuclear Materials and Energy, Vol 16, Iss , Pp 1-11 (2018)
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes are produced on the plasma-facing components (PFCs) by intense plasma bombardment, radiation and nuclear heating. For reliable ex
Externí odkaz:
https://doaj.org/article/c740c5a5462f40129b8c9c84b2f7bba1
Akademický článek
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Autor:
H. Greuner, F. Gallay, M. Fursdon, Eliseo Visca, G. Dose, Marianne Richou, F. Domptail, T.R. Barrett, Frank Schoofs, Adomas Lukenskas, S. Roccella, J.-H. You
Publikováno v:
Fusion Engineering and Design
This paper focuses on the development of the water-cooled divertor target concept known as Thermal Break, which was carried out in two phases. In Phase 1, six small scale mock-ups were fabricated and subjected to high heat flux (HHF) testing of up to
Publikováno v:
Fusion Engineering and Design
A high performing DEMO divertor target mock-up design that uses the thermal break interlayer concept is presented. The design evolved from a previous design of which six mock-ups were designed, fabricated and subjected to high heat flux testing. The
Autor:
A. Ash, A.J.T. Holmes, S. McIntosh, S. Zheng, K. Cave-Ayland, K. Hamada, F. Domptail, E. Surrey, Neil Mitchell, N. Taylor
Publikováno v:
Fusion Engineering and Design. 124:119-122
This arc model was motivated by the need to model arcs during the failure of a large superconducting magnet following an unmitigated quench. During a quench, resistive heating raises the conductor and insulator temperature. Electrical and mechanical
An integrated model for the assessment of unmitigated fault events in ITER's superconducting magnets
Autor:
Neil Mitchell, A.J.T. Holmes, S. McIntosh, A. Ash, F. Domptail, E. Surrey, N. Taylor, K. Cave-Ayland, S. Zheng, K. Hamada
Publikováno v:
Fusion Engineering and Design. :1559-1563
A large amount of energy is stored in ITER superconducting magnet system. Faults which initiate a discharge are typically mitigated to quickly transfer away the stored magnetic energy for dissipation through a bank of resistors. In an extreme unlikel
Autor:
A. Holmes, K. Cave-Ayland, E. Surrey, N. Mitchell, F. Domptail, N. Taylor, S. McIntosh, K. Hamada, A. Ash, A. Foussat, S. Zheng
Publikováno v:
IEEE Transactions on Applied Superconductivity. 26:1-5
Autor:
S. Roccella, B. Böswirth, Ch. Vorpahl, F. Crescenzi, H. Greuner, Eliseo Visca, B. E. Ghidersa, F. Domptail, M. Fursdon, Jeong-Ha You, M. Li, Marianne Richou, T.R. Barrett, J. Reiser, Alexander Müller, F. Gallay
Publikováno v:
Nuclear materials and energy, 16, 1–11
Nuclear Materials and Energy, Vol 16, Iss, Pp 1-11 (2018)
Nuclear Materials and Energy
Nuclear Materials and Energy, Vol 16, Iss, Pp 1-11 (2018)
Nuclear Materials and Energy
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes are produced on the plasma-facing components (PFCs) by intense plasma bombardment, radiation and nuclear heating. For reliable ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c4d6fa803b17a5d3a3bd0d1e0eda867a
https://publikationen.bibliothek.kit.edu/1000085927
https://publikationen.bibliothek.kit.edu/1000085927
Autor:
T. Barrett, Frederic Escourbiac, M. Fursdon, E. Surrey, F. Domptail, Triestino Minniti, Alexander Müller, A. Durocher, Llion Evans, Winfried Kockelmann, M. Gorley
Publikováno v:
Fusion Engineering and Design
Within a tokamak fusion energy device, the performance and lifespan of a divertor monoblock under high heat flux cycles is of particular interest. Key to this is the quality of manufacture, especially the material joining interfaces. Presented here i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::55d7b5f380379ec3b9bb4ed284c19854
https://hdl.handle.net/21.11116/0000-0002-075A-221.11116/0000-0002-075C-021.11116/0000-0005-F1A9-C
https://hdl.handle.net/21.11116/0000-0002-075A-221.11116/0000-0002-075C-021.11116/0000-0005-F1A9-C
Autor:
Eliseo Visca, M. Li, T.R. Barrett, M. Richou, Llion Evans, J.-H. You, N. Luzginova, M. Fursdon, N. H. Greuner, F. Domptail, F. Gallay
Publikováno v:
Physica Scripta
The design and development of a novel plasma facing component (for fusion power plants) is described. The component uses the existing 'monoblock' construction which consists of a tungsten 'block' joined via a copper interlayer to a through CuCrZr coo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cb6e1ddf954e4c9146c2a177023c6100
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85040122481&doi=10.1088/1402-4896/aa8c8e&partnerID=40&md5=2c6c1078c2ef129e49b4187186312148
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85040122481&doi=10.1088/1402-4896/aa8c8e&partnerID=40&md5=2c6c1078c2ef129e49b4187186312148