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http://arks.princeton.edu/ark:/88435/dsp01pc289m87q
Full metadata record
DC Field | Value | Language |
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dc.contributor.author | W.P. Wehner, E. Schuster, M.D. Boyer, F. Poli | - |
dc.date.accessioned | 2019-04-01T16:54:48Z | - |
dc.date.available | 2019-04-01T16:54:48Z | - |
dc.date.issued | 2019-04 | - |
dc.identifier.uri | http://arks.princeton.edu/ark:/88435/dsp01pc289m87q | - |
dc.description.abstract | An optimization approach that incorporates the predictive transport code TRANSP is proposed for tokamak scenario development. Optimization methods are often employed to develop open-loop control strategies to aid access to high performance tokamak scenarios. In general, the optimization approaches use control-oriented models, i.e. models that are reduced in complexity and prediction accuracy as compared to physics-oriented transport codes such as TRANSP. In the presented approach, an optimization procedure using the TRANSP code to simulate the tokamak plasma is considered for improved predictive capabilities. As a test case, the neutral beam injection (NBI) power is optimized to develop a control strategy that maximizes the non-inductive current fraction during the ramp-up phase for NSTX-U. Simulation studies towards the achievement of non-inductive ramp up in NSTX-U have already been carried out with the TRANSP code. The optimization-based approach proposed in this work is used to maximize the non-inductive current fraction during ramp-up in NSTX-U, demonstrating that the scenario development task can be automated. An additional test case considers optimization of the current ramp rate in DIII-D for obtaining a stationary plasma characterized by a flat loop voltage profile in the flattop phase. | en_US |
dc.description.tableofcontents | readme and digital data files | en_US |
dc.language.iso | en_US | en_US |
dc.publisher | Princeton Plasma Physics Laboratory, Princeton University | en_US |
dc.relation | Fusion Engineering and Design | en_US |
dc.subject | TRANSP | en_US |
dc.subject | scenario development | en_US |
dc.subject | optimal control design | en_US |
dc.subject | optimal plasma scenario planning | en_US |
dc.subject | NSTX-U | en_US |
dc.subject | DIII-D | en_US |
dc.title | TRANSP-based Optimization Towards Tokamak Scenario Development | en_US |
dc.type | Dataset | en_US |
dc.contributor.funder | U. S. Department of Energy | en_US |
Appears in Collections: | NSTX-U |
Files in This Item:
File | Description | Size | Format | |
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README.txt | 954 B | Text | View/Download | |
ARK_DATA.zip | 28.13 kB | Unknown | View/Download |
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