2018 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-1 Plasma Technology, including Inertial Confinement Fusion / 601-4 Reactor Component Technology, First Wall, Divertor, Magnet

[1N01-07] Engineering and Design for Nuclear Fusion (Heat and Mass-transfer Characteristic, Engineering Design)

Wed. Sep 5, 2018 10:00 AM - 11:55 AM Room N (D23 -D Building)

Chair:Teppei Otsuka(Kindai Univ.)

11:30 AM - 11:45 AM

[1N07] A fast discharge scheme of toroidal field coils for a fusion demo reactor

*yasuyuki Itoh1, Hiroyasu Utoh2,3, Yoshiteru Sakamoto2,3, Ryoji Hiwatari2,3 (1. Fukui University of Technology, 2. National Institutes for Quantum and Radiological Science and Technology, 3. Joint Special Design Team for Fusion DEMO)

Keywords:fusion demo reactor, toroidal field coil, fast discharge, insulation voltage, inductance

An inductance of toroidal field (TF) magnet in a fusion demo reactor is 3-4 times greater than that of ITER. The higher value of the inductance increases a turn insulation voltage generated in emergency fast discharge processes. We propose a fast discharge scheme of TF coils for avoiding the voltage increase with electrically dividing the magnet into two systems.