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Almaviva, S.*; Karino, Takahiro; Akaoka, Katsuaki; Wakaida, Ikuo
Spectrochimica Acta, Part B, 218, p.106960_1 - 106960_7, 2024/08
Mascari, F.*; Bersano, A.*; Woods, B. G.*; Reyes, J. N.*; Welter, K.*; Nakamura, Hideo; D'Auria, F.*
Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03
Bierwage, A.; Di Troia, C.*; Briguglio, S.*; Vlad, G.*
Computer Physics Communications, 183(5), p.1107 - 1123, 2012/05
Times Cited Count:11 Percentile:54.16(Computer Science, Interdisciplinary Applications)Gaio, E.*; Novello, L.*; Piovan, R.*; Shimada, Katsuhiro; Terakado, Tsunehisa; Kurihara, Kenichi; Matsukawa, Makoto
Fusion Engineering and Design, 84(2-6), p.804 - 809, 2009/06
Times Cited Count:20 Percentile:76.46(Nuclear Science & Technology)This paper deals with the conceptual design of the Quench Protection Circuits (QPC) of JT-60SA which have to provide a fast removal of the energy stored in the superconducting coils in case of quench. The core of the QPC units is constituted by a dc current breaker, which diverts the coil current into a resistor for a fast machine de-energization. In this paper, a hybrid solution, composed of a mechanical bypass switch paralleled to a static switch based on Integrated Gate Commutated Thyristor (IGCT) technology, has been chosen and worked out; a pyrobreaker is added in series to the hybrid switch as a backup protection. The resulting design allows benefiting from the fast breaking and very low maintenance requirement of the static switches, besides maintaining the advantage of the much lower power losses of the mechanical bypass in normal operation.
Bierwage, A.; Di Troia, C.*; Zonca, F.*
no journal, ,
Tommasi, G. D.*; Farthing, J.*; Joffrin, E.*; Vega, J.*; Vitale, V.*; Clement, S.*; Sartori, F.*; Kubo, Hirotaka; Nakajima, Noriyoshi*; Ozeki, Takahisa
no journal, ,
The ITER Remote Experimentation Centre is one of the projects currently under implementation within the International Fusion Energy Research Centre. The final objective of the REC is to allow researchers to take part in the experimentation on ITER from a remote location. This includes the possibility to receive in real-time information about the status of the machine and experimental data and to interact with the machine control room. This paper first gives an overview on the current status of the REC project, and then it focuses on a proposal for the REC demonstration to be carried out in collaboration with European Tokamaks. Finally, a possible implementation plan for the demonstration is discussed.
Tommasi, G. D.*; Farthing, J.*; Joffrin, E.*; Kubo, Hirotaka; Vitale, V.*; Clement, S.*; Sartori, F.*; Nakajima, Noriyoshi*; Ozeki, Takahisa
no journal, ,
The ITER Remote Experimentation Centre is one of the projects currently under implementation within the International Fusion Energy Research Centre. The final objective of the REC is to allow researchers to take part in the experimentation on ITER from a remote location. This includes the possibility to receive in real-time information about the status of the machine and experimental data and to interact with the machine control room. This paper first gives an overview on the current status of the REC project, and then it focuses on a proposal for the REC demonstration to be carried out in collaboration with European Tokamaks. Finally, a possible implementation plan for the demonstration is discussed.
Garzotti, L.*; Barbato, E.*; Garcia, J.*; Romanelli, M.*; Stankiewicz, R.*; Hayashi, Nobuhiko; Yoshida, Maiko
no journal, ,