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Title: Investigation of ion and electron heat transport of high-Te ECH heated discharges in the large helical device

Journal Article · · Plasma Physics and Controlled Fusion

An analysis of the radial electric field and heat transport, both for ions and electrons, is presented for a high-$${{T}_{\text{e}}}$$ electron cyclotron heated (ECH) discharge on the large helical device (LHD). Transport analysis is done using the task3d transport suite utilizing experimentally measured profiles for both ions and electrons. Ion temperature and perpendicular flow profiles are measured using the recently installed x-ray imaging crystal spectrometer diagnostic (XICS), while electron temperature and density profiles are measured using Thomson scattering. The analysis also includes calculated ECH power deposition profiles as determined through the travis ray-tracing code. This is the first time on LHD that this type of integrated transport analysis with measured ion temperature profiles has been performed without NBI, allowing the heat transport properties of plasmas with only ECH heating to be more clearly examined. For this study, a plasma discharge is chosen which develops a high central electron temperature ($${{T}_{\text{eo}}}=9$$ keV) at moderately low densities ($${{n}_{\text{eo}}}=1.5\times {{10}^{19}}$$ m-3). The experimentally determined transport properties from task3d are compared to neoclassical predictions as calculated by the gsrake and fortec-3d codes. The predicted electron fluxes are seen to be an order of magnitude less than the measured fluxes, indicating that electron transport is largely anomalous, while the neoclassical and measured ion heat fluxes are of the same magnitude. Neoclassical predictions of a strong positive ambipolar electric field ($${{E}_{\text{r}}}$$ ) in the plasma core are validated through comparisons to perpendicular flow measurements from the XICS diagnostic. Furthermore, this provides confidence that the predictions are producing physically meaningful results for the particle fluxes and radial electric field, which are a key component in correctly predicting plasma confinement.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Contributing Organization:
The LHD Experiment Group
Grant/Contract Number:
NIFS13KNST051; NIFS14KNTT025; AC02-09CH11466
OSTI ID:
1255638
Alternate ID(s):
OSTI ID: 1236289
Report Number(s):
PPPL-5138
Journal Information:
Plasma Physics and Controlled Fusion, Vol. 58, Issue 4; ISSN 0741-3335
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 7 works
Citation information provided by
Web of Science

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Cited By (2)

Stellarator Research Opportunities: A Report of the National Stellarator Coordinating Committee journal February 2018
Comparison of a 2D nonlocal transport model to ECRH experiments in LHD journal May 2019