Experimental demonstration of transient CHI start-up using a floating biased electrode configuration

Transient coaxial helicity injection (CHI) current start-up in a spherical tokamak (ST) has been demonstrated for the first time using a reactor-relevant floating single biased (FSB) electrode configuration on QUEST. Unlike previous applications of CHI on HIT-II and on NSTX in which the entire ST vessel was split in two using two toroidal ceramic rings as vacuum breaks, in the FSB electrode configuration on QUEST, only the lower outer divertor plate is electrically insulated from the rest of the vessel. This is the CHI injector region. A CHI discharge is generated by driving current, using an external power supply, along magnetic field lines that connect the inner and outer divertor plates in the CHI injector region. The CHI plasma evolution and closed flux formation on QUEST are very similar to those on NSTX and have generated toroidal currents of 150 kA with 100 kA of current flowing on closed flux surfaces. An alternate, force-free model approach has been used to derive the CHI scaling relations. The resulting CHI scaling relations from the model are consistent with the conventional CHI scaling relations, which state that the CHI generated toroidal current is proportional to the CHI injector flux and the CHI injector current is inversely proportional to the toroidal field. These results from QUEST bode well for the application of CHI in a new generation of compact high field STs and low aspect ratio tokamaks in which the space for the central solenoid is very restricted.

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Publication Details

Journal
Physics of Plasmas
Published
2025-04-01
DOI
https://doi.org/10.1063/5.0259035
Citations
1
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
1.87

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Experimental demonstration of transient CHI start-up using a floating biased electrode configuration

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article

Experimental demonstration of transient CHI start-up using a floating biased electrode configuration

T. Onchi, R. Ikezoe, Makoto Hasegawa, N. Nishino, R. Raman, Izumi Sekiya, O. Mitarai, M. Ono, K. Kuroda, T. Ido, Masayoshi Nagata, Takanori Motoki, John A. Rogers, A. Higashijima, T. Kanki, S. Shimabukuro, S. Murakami, K. Kono, H. Idei, A. Ejiri, Takahiro Nagata, Yuji Otsuka, K. Nakamura, Isao NIIYA, Kazuaki Hanada, S. Kawasaki
article en
1 citations

Abstract

Transient coaxial helicity injection (CHI) current start-up in a spherical tokamak (ST) has been demonstrated for the first time using a reactor-relevant floating single biased (FSB) electrode configuration on QUEST. Unlike previous applications of CHI on HIT-II and on NSTX in which the entire ST vessel was split in two using two toroidal ceramic rings as vacuum breaks, in the FSB electrode configuration on QUEST, only the lower outer divertor plate is electrically insulated from the rest of the vessel. This is the CHI injector region. A CHI discharge is generated by driving current, using an external power supply, along magnetic field lines that connect the inner and outer divertor plates in the CHI injector region. The CHI plasma evolution and closed flux formation on QUEST are very similar to those on NSTX and have generated toroidal currents of 150 kA with 100 kA of current flowing on closed flux surfaces. An alternate, force-free model approach has been used to derive the CHI scaling relations. The resulting CHI scaling relations from the model are consistent with the conventional CHI scaling relations, which state that the CHI generated toroidal current is proportional to the CHI injector flux and the CHI injector current is inversely proportional to the toroidal field. These results from QUEST bode well for the application of CHI in a new generation of compact high field STs and low aspect ratio tokamaks in which the space for the central solenoid is very restricted.

Physics of PlasmasVol. 32(4)
Kyushu University (JP), University of Hyogo (JP), University of Washington (US), Kyoto University (JP), Princeton Plasma Physics Laboratory (US), Japan Coast Guard Academy (JP), The University of Tokyo (JP), Kyushu Tokai University (JP)
U.S. Department of Energy, National Institute for Fusion Science
Openalex Percentile: Top 15%
Magnetic confinement fusion research
1.87
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