NSTX-U theory, modeling and analysis results
<jats:title>Abstract</jats:title> <jats:p>The mission of the low aspect ratio spherical tokamak NSTX-U is to advance the physics basis and technical solutions required for optimizing the configuration of next-step steady-state tokamak fusion devices. NSTX-U will ult...
| Main Author: | |
|---|---|
| Other Authors: | |
| Format: | Article |
| Language: | English |
| Published: |
IOP Publishing
2023
|
| Online Access: | https://hdl.handle.net/1721.1/150339 |
| _version_ | 1826212416167346176 |
|---|---|
| author | White, Anne |
| author2 | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering |
| author_facet | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering White, Anne |
| author_sort | White, Anne |
| collection | MIT |
| description | <jats:title>Abstract</jats:title>
<jats:p>The mission of the low aspect ratio spherical tokamak NSTX-U is to advance the physics basis and technical solutions required for optimizing the configuration of next-step steady-state tokamak fusion devices. NSTX-U will ultimately operate at up to 2 MA of plasma current and 1 T toroidal field on axis for 5 s, and has available up to 15 MW of neutral beam injection power at different tangency radii and 6 MW of high harmonic fast wave heating. With these capabilities NSTX-U will develop the physics understanding and control tools to ramp-up and sustain high performance fully non-inductive plasmas with large bootstrap fraction and enhanced confinement enabled via the low aspect ratio, high beta configuration. With its unique capabilities, NSTX-U research also supports ITER and other critical fusion development needs. Super-Alfvénic ions in beam-heated NSTX-U plasmas access energetic particle (EP) parameter space that is relevant for both α-heated conventional and low aspect ratio burning plasmas. NSTX-U can also generate very large target heat fluxes to test conventional and innovative plasma exhaust and plasma facing component solutions. This paper summarizes recent analysis, theory and modelling progress to advance the tokamak physics basis in the areas of macrostability and 3D fields, EP stability and fast ion transport, thermal transport and pedestal structure, boundary and plasma material interaction, RF heating, scenario optimization and real-time control.</jats:p> |
| first_indexed | 2024-09-23T15:21:19Z |
| format | Article |
| id | mit-1721.1/150339 |
| institution | Massachusetts Institute of Technology |
| language | English |
| last_indexed | 2024-09-23T15:21:19Z |
| publishDate | 2023 |
| publisher | IOP Publishing |
| record_format | dspace |
| spelling | mit-1721.1/1503392023-04-04T03:07:17Z NSTX-U theory, modeling and analysis results White, Anne Massachusetts Institute of Technology. Department of Nuclear Science and Engineering <jats:title>Abstract</jats:title> <jats:p>The mission of the low aspect ratio spherical tokamak NSTX-U is to advance the physics basis and technical solutions required for optimizing the configuration of next-step steady-state tokamak fusion devices. NSTX-U will ultimately operate at up to 2 MA of plasma current and 1 T toroidal field on axis for 5 s, and has available up to 15 MW of neutral beam injection power at different tangency radii and 6 MW of high harmonic fast wave heating. With these capabilities NSTX-U will develop the physics understanding and control tools to ramp-up and sustain high performance fully non-inductive plasmas with large bootstrap fraction and enhanced confinement enabled via the low aspect ratio, high beta configuration. With its unique capabilities, NSTX-U research also supports ITER and other critical fusion development needs. Super-Alfvénic ions in beam-heated NSTX-U plasmas access energetic particle (EP) parameter space that is relevant for both α-heated conventional and low aspect ratio burning plasmas. NSTX-U can also generate very large target heat fluxes to test conventional and innovative plasma exhaust and plasma facing component solutions. This paper summarizes recent analysis, theory and modelling progress to advance the tokamak physics basis in the areas of macrostability and 3D fields, EP stability and fast ion transport, thermal transport and pedestal structure, boundary and plasma material interaction, RF heating, scenario optimization and real-time control.</jats:p> 2023-04-03T15:07:10Z 2023-04-03T15:07:10Z 2022 2023-04-03T13:41:42Z Article http://purl.org/eprint/type/JournalArticle https://hdl.handle.net/1721.1/150339 White, Anne. 2022. "NSTX-U theory, modeling and analysis results." Nuclear Fusion, 62 (4). en 10.1088/1741-4326/AC5448 Nuclear Fusion Creative Commons Attribution-Noncommercial-Share Alike http://creativecommons.org/licenses/by-nc-sa/4.0/ application/pdf IOP Publishing DOE repository |
| spellingShingle | White, Anne NSTX-U theory, modeling and analysis results |
| title | NSTX-U theory, modeling and analysis results |
| title_full | NSTX-U theory, modeling and analysis results |
| title_fullStr | NSTX-U theory, modeling and analysis results |
| title_full_unstemmed | NSTX-U theory, modeling and analysis results |
| title_short | NSTX-U theory, modeling and analysis results |
| title_sort | nstx u theory modeling and analysis results |
| url | https://hdl.handle.net/1721.1/150339 |
| work_keys_str_mv | AT whiteanne nstxutheorymodelingandanalysisresults |