Abstract
Energy confinement time and thermal transport have been investigated in NBI heated hydrogen (H), deuterium (D), and mixture (H&D, H&D&He) plasmas in a large-scale stellarator-heliotron LHD. Comparison of H and D plasmas has not shown significant mass dependence in energy confinement time, which is not consistent with unfavourable mass dependence predicted by a gyro-Bohm model. Nonetheless, different aspect emerges when the scaling expression of energy confinement is rephrased into dimensionless parameters. The expression in dimensionless parameters ? Escl,thOi f M 0.99 ?* -2.98 suggests co-existence of a clear mass dependence and gyro-Bohm nature. Comparison of thermal diffusivity for dimensionally similar H and D plasmas in terms of ?*, ?*, and ß has clearly shown robust confinement improvement in deuterium to compensate unfavorable mass dependence predicted by the gyro-Bohm model. Whichever mixture plasmas of H and D, or H,D, and He lie on the scaling derived from H and D plasmas. Even regression analysis of energy confinement time including M and Zeff of extended dataset including mixture plasmas has shown significant dependence on neither M nor Zeff.
Original language | English |
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State | Published - 2019 |
Externally published | Yes |
Event | 46th European Physical Society Conference on Plasma Physics, EPS 2019 - Milan, Italy Duration: Jul 8 2019 → Jul 12 2019 |
Conference
Conference | 46th European Physical Society Conference on Plasma Physics, EPS 2019 |
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Country/Territory | Italy |
City | Milan |
Period | 07/8/19 → 07/12/19 |
Funding
The authors are grateful to the technical staff of LHD for their excellent support for this work. This work is supported by the National Institute for Fusion Science grant administrative budgets (NIFS19KLPH038, NIFS17UNTT008) and JSPS KAKENHI Grant Numbers JP17H01368. of LHD for their excellent support for this work. This work is supported by the National
Funders | Funder number |
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National | |
Japan Society for the Promotion of Science | JP17H01368 |
National Institute for Fusion Science | NIFS17UNTT008, NIFS19KLPH038 |