Abstract
The research plan of the JT-60SA, a superconducting tokamak device currently under construction, requests a powerful pellet injection system for its particle fueling and edge-localized-mode (ELM) pacing experiments. These investigations, foreseen to answer basic questions with respect to the operation of ITER and a future fusion power plant like DEMO, need pellets with flexible parameters delivered precisely and reliably for control purposes. Here, we present a conceptual design of this system based on classical pellet technology. Analysis showed pellets will show the best performance for fueling and most likely also for ELM pacing when injected from the torus inboard side, despite the limited maximum pellet speed caused by this approach. This is due to constructional constraints rising from the fact the JT-60SA vacuum vessel is already under construction, enforcing inboard injection via a multibend guiding-tube system and limiting the maximum pellet speed to about 470 m/s. To match this boundary condition and fulfill the need for precise control, a centrifuge accelerator has been chosen. Based on the stop cylinder principle and equipped with a double accelerator arm, it can host up to six steady-state ice extruders working simultaneously for pellet production. This way, all system requirements expressed in the research plan can be well covered, providing even some headroom for better flexibility during the planned investigations. Details of our design and the reasoning for the layout chosen are provided in this paper.
Highlights
A new superconducting tokamak is currently being built under the Broader Approach Satellite Tokamak Programme run jointly by Europe and Japan, and under the Japanese national program
We present a conceptual design of this system based on classical pellet technology
Analysis showed pellets will show the best performance for fueling and most likely for ELM pacing when injected from the torus inboard side, despite the limited maximum pellet speed caused by this approach
Summary
A new superconducting tokamak is currently being built under the Broader Approach Satellite Tokamak Programme run jointly by Europe and Japan, and under the Japanese national program. The startup of operation of such a large experimental device is a challenging enterprise, requiring a broad set of preparation activities that involve among others the elaboration of a research plan[2] and conception studies of diagnostics and subsystems, for example, heating, matter injection, and pumping Many of these activities are carried out in a FLEXIBLE PELLET INJECTION SYSTEM FOR THE TOKAMAK JT-60SA · LANG et al 179 coordinated way by a joint Japan-European Union (EU) JT-60SA Research Unit, in close interaction with the JT-60SA project for the machine construction.[1] One activity of this kind was the conceptual design of the pellet injection system, requested to be elaborated on in a dedicated study within 3 years. The outcome of this study, finalized in 2017, is presented in this paper
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