Flexible, integrated modeling of tokamak stability, transport, equilibrium, and pedestal physics
Abstract
The STEP (Stability, Transport, Equilibrium, and Pedestal) integrated-modeling tool has been developed in OMFIT to predict stable, tokamak equilibria self-consistently with core-transport and pedestal calculations. STEP couples theory-based codes to integrate a variety of physics, including MHD stability, transport, equilibrium, pedestal formation, and current-drive, heating, and fueling. The input/output of each code is interfaced with a centralized ITER-IMAS data structure, allowing codes to be run in any order and enabling open-loop, feedback, and optimization work-flows. This paradigm simplifies the integration of new codes, making STEP highly extensible. STEP has been verified against a published benchmark of six differ-ent integrated models. Core-pedestal calculations with STEP have been successfully validated against individual DIII-D H-mode discharges and across more than 500 dis-charges of the H98,y2 database, with a mean error in confinement time from experiment less than 19%. STEP has also reproduced results in less conventional DIII-D scenar-ios, including negative-central-shear and negative-triangularity plasmas. Predictive STEP modeling has been used to assess performance in several tokamak reactors. Simulations of a high-field, large-aspect-ratio reactor show significantly lower fusion power than predicted by a zero-dimensional study, demonstrating the limitations of scaling-law extrapolations. STEP predictions have found promising scenarios for an EXhaust and Confinement Integration Tokamak Experimentmore »
- Authors:
- Publication Date:
- Research Org.:
- General Atomics, San Diego, CA
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1996416
- Grant/Contract Number:
- FG02-95ER54309; FC02-04ER54698; SC0017992; AC02-05CH11231
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Physics of Plasmas (PoP)
- Additional Journal Information:
- Journal Name: Physics of Plasmas (PoP); Journal Volume: 30; Journal Issue: 9; Journal ID: ISSN 1070--664X
- Country of Publication:
- United States
- Language:
- English
Citation Formats
Lyons, Brendan, McClenaghan, J., Slendebroek, T., Meneghini, O., Neiser, T., Smith, S., Weisberg, D., Belli, E., Candy, J., Hanson, J., Lao, L., Logan, N., Saarelma, S., Sauter, O., Snyder, P., Staebler, G., Thome, K., and Turnbull, A. Flexible, integrated modeling of tokamak stability, transport, equilibrium, and pedestal physics. United States: N. p., 2023.
Web. doi:10.1063/5.0156877.
Lyons, Brendan, McClenaghan, J., Slendebroek, T., Meneghini, O., Neiser, T., Smith, S., Weisberg, D., Belli, E., Candy, J., Hanson, J., Lao, L., Logan, N., Saarelma, S., Sauter, O., Snyder, P., Staebler, G., Thome, K., & Turnbull, A. Flexible, integrated modeling of tokamak stability, transport, equilibrium, and pedestal physics. United States. https://doi.org/10.1063/5.0156877
Lyons, Brendan, McClenaghan, J., Slendebroek, T., Meneghini, O., Neiser, T., Smith, S., Weisberg, D., Belli, E., Candy, J., Hanson, J., Lao, L., Logan, N., Saarelma, S., Sauter, O., Snyder, P., Staebler, G., Thome, K., and Turnbull, A. Sun .
"Flexible, integrated modeling of tokamak stability, transport, equilibrium, and pedestal physics". United States. https://doi.org/10.1063/5.0156877. https://www.osti.gov/servlets/purl/1996416.
@article{osti_1996416,
title = {Flexible, integrated modeling of tokamak stability, transport, equilibrium, and pedestal physics},
author = {Lyons, Brendan and McClenaghan, J. and Slendebroek, T. and Meneghini, O. and Neiser, T. and Smith, S. and Weisberg, D. and Belli, E. and Candy, J. and Hanson, J. and Lao, L. and Logan, N. and Saarelma, S. and Sauter, O. and Snyder, P. and Staebler, G. and Thome, K. and Turnbull, A.},
abstractNote = {The STEP (Stability, Transport, Equilibrium, and Pedestal) integrated-modeling tool has been developed in OMFIT to predict stable, tokamak equilibria self-consistently with core-transport and pedestal calculations. STEP couples theory-based codes to integrate a variety of physics, including MHD stability, transport, equilibrium, pedestal formation, and current-drive, heating, and fueling. The input/output of each code is interfaced with a centralized ITER-IMAS data structure, allowing codes to be run in any order and enabling open-loop, feedback, and optimization work-flows. This paradigm simplifies the integration of new codes, making STEP highly extensible. STEP has been verified against a published benchmark of six differ-ent integrated models. Core-pedestal calculations with STEP have been successfully validated against individual DIII-D H-mode discharges and across more than 500 dis-charges of the H98,y2 database, with a mean error in confinement time from experiment less than 19%. STEP has also reproduced results in less conventional DIII-D scenar-ios, including negative-central-shear and negative-triangularity plasmas. Predictive STEP modeling has been used to assess performance in several tokamak reactors. Simulations of a high-field, large-aspect-ratio reactor show significantly lower fusion power than predicted by a zero-dimensional study, demonstrating the limitations of scaling-law extrapolations. STEP predictions have found promising scenarios for an EXhaust and Confinement Integration Tokamak Experiment (EXCITE), including a high-pressure, 80%-bootstrap-fraction plasma. ITER modeling with STEP has shown that pellet fueling enhances fusion gain in both the baseline and advanced-inductive scenarios. Finally, STEP predictions for the SPARC baseline scenario are in good agreement with published results from the physics basis.},
doi = {10.1063/5.0156877},
journal = {Physics of Plasmas (PoP)},
number = 9,
volume = 30,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2023},
month = {Sun Jan 01 00:00:00 EST 2023}
}
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