CORSICA modelling of ITER hybrid operation scenarios
Abstract
The hybrid operating mode observed in several tokamaks is characterized by further enhancement over the high plasma confinement (H-mode) associated with reduced magneto-hydro-dynamic (MHD) instabilities linked to a stationary flat safety factor ($$q$$ ) profile in the core region. The proposed ITER hybrid operation is currently aiming at operating for a long burn duration (>1000 s) with a moderate fusion power multiplication factor, $$Q$$ , of at least 5. This paper presents here candidate ITER hybrid operation scenarios developed using a free-boundary transport modelling code, CORSICA, taking all relevant physics and engineering constraints into account. The ITER hybrid operation scenarios have been developed by tailoring the 15 MA baseline ITER inductive H-mode scenario. Accessible operation conditions for ITER hybrid operation and achievable range of plasma parameters have been investigated considering uncertainties on the plasma confinement and transport. ITER operation capability for avoiding the poloidal field coil current, field and force limits has been examined by applying different current ramp rates, flat-top plasma currents and densities, and pre-magnetization of the poloidal field coils. Various combinations of heating and current drive (H&CD) schemes have been applied to study several physics issues, such as the plasma current density profile tailoring, enhancement of the plasma energy confinement and fusion power generation. A parameterized edge pedestal model based on EPED1 added to the CORSICA code has been applied to hybrid operation scenarios. Finally, fully self-consistent free-boundary transport simulations have been performed to provide information on the poloidal field coil voltage demands and to study the controllability with the ITER controllers.
- Authors:
-
- ITER Organization, St. Paul Lez Durance (France)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); ITER Organization, St. Paul Lez Durance (France)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1502010
- Report Number(s):
- LLNL-JRNL-756688
Journal ID: ISSN 0029-5515; 943988
- Grant/Contract Number:
- AC52-07NA27344
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Volume: 56; Journal Issue: 12; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Citation Formats
Kim, S. H., Bulmer, R. H., Campbell, D. J., Casper, T. A., LoDestro, L. L., Meyer, W. H., Pearlstein, L. D., and Snipes, J. A.. CORSICA modelling of ITER hybrid operation scenarios. United States: N. p., 2016.
Web. doi:10.1088/0029-5515/56/12/126002.
Kim, S. H., Bulmer, R. H., Campbell, D. J., Casper, T. A., LoDestro, L. L., Meyer, W. H., Pearlstein, L. D., & Snipes, J. A.. CORSICA modelling of ITER hybrid operation scenarios. United States. https://doi.org/10.1088/0029-5515/56/12/126002
Kim, S. H., Bulmer, R. H., Campbell, D. J., Casper, T. A., LoDestro, L. L., Meyer, W. H., Pearlstein, L. D., and Snipes, J. A.. Wed .
"CORSICA modelling of ITER hybrid operation scenarios". United States. https://doi.org/10.1088/0029-5515/56/12/126002. https://www.osti.gov/servlets/purl/1502010.
@article{osti_1502010,
title = {CORSICA modelling of ITER hybrid operation scenarios},
author = {Kim, S. H. and Bulmer, R. H. and Campbell, D. J. and Casper, T. A. and LoDestro, L. L. and Meyer, W. H. and Pearlstein, L. D. and Snipes, J. A.},
abstractNote = {The hybrid operating mode observed in several tokamaks is characterized by further enhancement over the high plasma confinement (H-mode) associated with reduced magneto-hydro-dynamic (MHD) instabilities linked to a stationary flat safety factor ($q$ ) profile in the core region. The proposed ITER hybrid operation is currently aiming at operating for a long burn duration (>1000 s) with a moderate fusion power multiplication factor, $Q$ , of at least 5. This paper presents here candidate ITER hybrid operation scenarios developed using a free-boundary transport modelling code, CORSICA, taking all relevant physics and engineering constraints into account. The ITER hybrid operation scenarios have been developed by tailoring the 15 MA baseline ITER inductive H-mode scenario. Accessible operation conditions for ITER hybrid operation and achievable range of plasma parameters have been investigated considering uncertainties on the plasma confinement and transport. ITER operation capability for avoiding the poloidal field coil current, field and force limits has been examined by applying different current ramp rates, flat-top plasma currents and densities, and pre-magnetization of the poloidal field coils. Various combinations of heating and current drive (H&CD) schemes have been applied to study several physics issues, such as the plasma current density profile tailoring, enhancement of the plasma energy confinement and fusion power generation. A parameterized edge pedestal model based on EPED1 added to the CORSICA code has been applied to hybrid operation scenarios. Finally, fully self-consistent free-boundary transport simulations have been performed to provide information on the poloidal field coil voltage demands and to study the controllability with the ITER controllers.},
doi = {10.1088/0029-5515/56/12/126002},
journal = {Nuclear Fusion},
number = 12,
volume = 56,
place = {United States},
year = {2016},
month = {8}
}
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