Výsledky vyhledávání - "Experimental reactors"

Beam energy recovery for fusion and collector design for tests on compact sources

Autor: V. Variale, Emanuele Sartori, C. Baltador, M. Cavenago, V. Valentino, G. Serianni

Publikováno v: Review of scientific instruments 91 (2020): 013516-1–013516-5. doi:10.1063/1.5128668
info:cnr-pdr/source/autori:Variale, V.; Valentino, V.; Cavenago, M.; Baltador, C.; Sartori, E.; Serianni, G./titolo:Beam energy recovery for fusion and collector design for tests on compact sources/doi:10.1063%2F1.5128668/rivista:Review of scientific instruments/anno:2020/pagina_da:013516-1/pagina_a:013516-5/intervallo_pagine:013516-1–013516-5/volume:91

The next fusion project DEMO, which will be the evolution of the experimental fusion reactor [International Tokamak Experimental Reactor (ITER)], would require a high efficient energy production. As in ITER, DEMO will use fast Neutral Beam (NB) injec

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a23f0bc145a04835eee6ae19159c319f
https://pubmed.ncbi.nlm.nih.gov/32012581

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Proposal for halo current diagnostic system for JET

Autor: V. Riccardo, Pietro Fiorentin, T. Bolzonella, Simone Peruzzo, N. Pomaro, Luca Grando, Piergiorgio Sonato

Publikováno v: Review of scientific instruments 74 (2003): 1567–1570. doi:10.1063/1.1526932
info:cnr-pdr/source/autori:Pomaro N.; Bolzonella T.; Fiorentin P.; Grando L.; Peruzzo S.; Riccardo V.; Sonato P./titolo:Proposal for halo current diagnostic system for JET/doi:10.1063%2F1.1526932/rivista:Review of scientific instruments/anno:2003/pagina_da:1567/pagina_a:1570/intervallo_pagine:1567–1570/volume:74

One of the critical issues for the International Thermonuclear Experimental Reactor is a deep understanding of the origin, distribution, and scaling of halo currents flowing through plasma and vacuum vessel during vertical displacement events. The Jo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ff10e745c67f6dfed13438ae7d846bb9
https://doi.org/10.1063/1.1526932

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Plasma position and shape control for ITER

Autor: D.J. Ward, M. Huguet, C.E. Kessel, R. Albanese, L.D. Pearlstein, D. Ciscato, A. Portone, P.L. Mondino, Y. Gribov, D.A. Humphreys

Publikováno v: ResearcherID
Scopus-Elsevier

Key features and main results about the control of the plasma shape in ITER are presented. A control algorithm is designed to control up to 6 gaps between the plasma separatrix and the plasma facing components during the reference burn phase. Nonline

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::af3e56c45fde6fb1fb165b27487efbdb
https://doi.org/10.1109/fusion.1995.534238

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R&D on support to ITER safety assessment

Autor: Ahmed Bentaib, Didier Perrault, J. Vendel, J. Bez, J. P. Van Dorsselaere, M. Barrachin, C. Seropian, P.Cortès, N. Trégourès

Publikováno v: Fusion Engineering and Design
Fusion Engineering and Design, 2009, 84 (7-11), pp.1905-1911. ⟨10.1016/j.fusengdes.2008.11.091⟩

After performing its first ITER safety assessment in 2002 on behalf of the French "Autorité de Sûreté Nucléaire (ASN)", the French "Institut de Radioprotection et de Sûreté Nucléaire (IRSN)" is now analysing the new ITER Fusion facility safety

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::82f2b52832646b7717159f347b275827
https://hal.archives-ouvertes.fr/hal-02988588

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Analysis of the ITER ECH Upper Port Launcher remote maintenance using virtual reality

All ITER sub-systems of remote handling (RH) classes 1 and 2 have to be remotely maintainable. The maintenance strategy for these components has to ensure system availability after failure or scheduled maintenance. This paper shows how virtual realit

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dris___00893::c3f00e3bd4601491eddba81eee981d94
http://resolver.tudelft.nl/uuid:6b596b7a-7aff-4990-bba9-8014d0991198

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Conceptual design of the ITER upper port plug for charge exchange diagnostic

Autor: Wolfgang Biel, N. C. Hawkes, M. Knaup, S. Sadakov, G. Kiss, Olaf Neubauer, Andrey Litnovsky, F. Klinkhamer, P. Gille, V. Borsuk, Yu. Krasikov, T. Baross, M. von Hellermann, J.F. Koning, Anatoly Panin

Publikováno v: Fusion Engineering and Design, 7-11, 84, 1671-1675
STARTPAGE=1671;ENDPAGE=1675;TITLE=None

A plug for the ITER core charge exchange recombination spectroscopy (core CXRS) is located in the upper port 3. It transfers the light emitted by interaction of plasma ions with the diagnostic neutral beam (DNB). The plug consists of a main shell, a

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0a7c4397c2840da72fa1f5dc4b5c7f1b
http://resolver.tudelft.nl/uuid:62b91670-ff52-4642-84ed-4c633b844b65

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Finalization of the conceptual design of the remote steering ECH launcher for ITER

Autor: Marco de Baar, Michiel Houkema, René Chavan, Marieke Hannink, M.F. Graswinckel, Fred de Vreede, W.A. Bongers, Dennis Ronden, Miranda van den Berg

Publikováno v: Fusion Engineering and Design, 7-11, 84, 1645-1648
STARTPAGE=1645;ENDPAGE=1648;TITLE=None

The design of a remote steering (RS) variant of the electron cyclotron heating (ECH) upper port launcher (UPL) for neo-classical tearing mode (NTM) stabilization in ITER is being finalised. The RS variant is the fall-back option for the reference des

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::082f61610f7742a972d861ab7061d44f
http://resolver.tudelft.nl/uuid:b8dd3927-2526-4f52-9fda-0f683d9ab5b5

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Analysis of the ITER ECH Upper Port Launcher remote maintenance using virtual reality

Autor: Marco de Baar, René Chavan, K. Kleefeldt, Timothy Goodman, Cock J.M. Heemskerk, R. Heidinger, Toon Verhoeven, S. Sanders, P. Späh, D. Strauss, J.F. Koning, Fred de Vreede, B.S.Q. Elzendoorn

Publikováno v: STARTPAGE=733;ENDPAGE=735;TITLE=None
Fusion Engineering and Design, 2-6, 84, 733-735

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c8e6716bb2bfe4d15b2334d89a383ae5
https://www.differ.nl/bibcite/reference/7017

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Magnetic island localization for NTM control by ECE viewed along the same optical path of the ECCD beam

Autor: Textor Team, A. P. H. Goede, W.A. Bongers, W. Wubie, Niek Doelman, J. Stober, D. Wagner, W. Kasparek, E. Westerhof, M.R. de Baar, J.W. Oosterbeek, F. C. Schüller

Publikováno v: Fusion Science and Technology, 55, 188-203
Fusion Science and Technology
Scopus-Elsevier
Fusion Science and Technology, 2, 55, 188-203

Neoclassical tearing modes (NTMs) deteriorate high-pressure tokamak plasma confinement and can be suppressed by electron cyclotron current drive (ECCD). In order to obtain efficient suppression, the ECCD power needs to be deposited at the center of a

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::86205d523edfda0267e8caa701dee633
https://www.differ.nl/bibcite/reference/7119

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Maintenance implications of critical components in ITER CXRS upper port plug design

Already in the early phase of a design for ITER, the maintenance aspects should be taken into account, since they might have serious implications. This paper presents the arguments in support of the case for the maintainability of the design, notably

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dris___00893::0a124ac4904c8ccf520425de8a58cb54
http://resolver.tudelft.nl/uuid:dc2939c3-6662-4dfa-a9ea-50e20a548554

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