Scaling-up capabilities of TRACE integral reactor nodalization against natural circulation phenomena in small modular reactors

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

Conceptual design of the quench protection circuits for the JT-60SA superconducting magnets

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

https://doi.org/10.1016/j.fusengdes.2008.12.100

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.

Modeling of JT-60SA operational scenarios

Garzotti, L.*; Barbato, E.*; Garcia, J.*; Romanelli, M.*; Stankiewicz, R.*; Hayashi, Nobuhiko; Yoshida, Maiko

no journal, , 

A Proposal for the demonstration of the ITER Remote Experimentation Centre with collaborating European Tokamaks

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.