skip to main content

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

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.
 [1] ;  [2] ;  [2] ; ORCiD logo [1] ;  [1] ;  [1] ; ORCiD logo [1] ;  [3] ;  [4] ;  [1] ;  [4] ;  [4] ; ORCiD logo [1] ;  [5] ; ORCiD logo [1] ;  [2] ;  [2] ;  [4] ;  [4] ;  [4] more »;  [2] ;  [4] ;  [2] ;  [4] « less
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. National Institute for Fusion Science, Gifu (Japan); SOKENDAI (The Graduate Univ. for Advanced Studies), Gifu (Japan)
  3. Max-Planck-Institut fur Plasmaphysik, Greifswald (Germany)
  4. National Institute for Fusion Science, Gifu (Japan)
  5. Research Organization for Information Science and Technology, Hyogo (Japan)
Publication Date:
OSTI Identifier:
Report Number(s):
Journal ID: ISSN 0741-3335
Grant/Contract Number:
NIFS13KNST051; NIFS14KNTT025; AC02-09CH11466
Accepted Manuscript
Journal Name:
Plasma Physics and Controlled Fusion
Additional Journal Information:
Journal Volume: 58; Journal Issue: 4; Journal ID: ISSN 0741-3335
IOP Science
Research Org:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Contributing Orgs:
The LHD Experiment Group
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; stellarator; transport; radial electric field; neoclassical; large helical device; x-ray imaging crystal spectrometer; core electron-root confinement