Implementation of the 3D edge plasma code EMC3-EIRENE on NSTX
Abstract
The 3D edge transport code EMC3-EIRENE has been applied for the first time to the NSTX spherical tokamak. A new disconnected double null grid has been developed to allow the simulation of plasma where the radial separation of the inner and outer separatrix is less than characteristic widths (e.g. heat flux width) at the midplane. Modelling results are presented for both an axisymmetric case and a case where 3D magnetic field is applied in an n = 3 configuration. In the vacuum approximation, the perturbed field consists of a wide region of destroyed flux surfaces and helical lobes which are a mixture of long and short connection length field lines formed by the separatrix manifolds. This structure is reflected in coupled 3D plasma fluid (EMC3) and kinetic neutral particle (EIRENE) simulations. The helical lobes extending inside of the unperturbed separatrix are filled in by hot plasma from the core. The intersection of the lobes with the divertor results in a striated flux footprint pattern on the target plates. As a result, profiles of divertor heat and particle fluxes are compared with experimental data, and possible sources of discrepancy are discussed.
- Authors:
-
- Oak Ridge Institute for Science and Education, Oak Ridge, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Max-Planck-Institut fur Plasmaphysik, Greifswald (Germany)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1239217
- Report Number(s):
- LLNL-JRNL-489125
Journal ID: ISSN 0029-5515; TRN: US1600616
- Grant/Contract Number:
- AC52-07NA27344
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Volume: 52; Journal Issue: 5; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION
Citation Formats
Lore, J. D., Canik, J. M., Feng, Y., Ahn, J. -W., Maingi, R., and Soukhanovskii, V. Implementation of the 3D edge plasma code EMC3-EIRENE on NSTX. United States: N. p., 2012.
Web. doi:10.1088/0029-5515/52/5/054012.
Lore, J. D., Canik, J. M., Feng, Y., Ahn, J. -W., Maingi, R., & Soukhanovskii, V. Implementation of the 3D edge plasma code EMC3-EIRENE on NSTX. United States. https://doi.org/10.1088/0029-5515/52/5/054012
Lore, J. D., Canik, J. M., Feng, Y., Ahn, J. -W., Maingi, R., and Soukhanovskii, V. Wed .
"Implementation of the 3D edge plasma code EMC3-EIRENE on NSTX". United States. https://doi.org/10.1088/0029-5515/52/5/054012. https://www.osti.gov/servlets/purl/1239217.
@article{osti_1239217,
title = {Implementation of the 3D edge plasma code EMC3-EIRENE on NSTX},
author = {Lore, J. D. and Canik, J. M. and Feng, Y. and Ahn, J. -W. and Maingi, R. and Soukhanovskii, V.},
abstractNote = {The 3D edge transport code EMC3-EIRENE has been applied for the first time to the NSTX spherical tokamak. A new disconnected double null grid has been developed to allow the simulation of plasma where the radial separation of the inner and outer separatrix is less than characteristic widths (e.g. heat flux width) at the midplane. Modelling results are presented for both an axisymmetric case and a case where 3D magnetic field is applied in an n = 3 configuration. In the vacuum approximation, the perturbed field consists of a wide region of destroyed flux surfaces and helical lobes which are a mixture of long and short connection length field lines formed by the separatrix manifolds. This structure is reflected in coupled 3D plasma fluid (EMC3) and kinetic neutral particle (EIRENE) simulations. The helical lobes extending inside of the unperturbed separatrix are filled in by hot plasma from the core. The intersection of the lobes with the divertor results in a striated flux footprint pattern on the target plates. As a result, profiles of divertor heat and particle fluxes are compared with experimental data, and possible sources of discrepancy are discussed.},
doi = {10.1088/0029-5515/52/5/054012},
journal = {Nuclear Fusion},
number = 5,
volume = 52,
place = {United States},
year = {Wed May 09 00:00:00 EDT 2012},
month = {Wed May 09 00:00:00 EDT 2012}
}
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Works referencing / citing this record:
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