Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

TRANSP-based optimization towards tokamak scenario development

Journal Article · · Fusion Engineering and Design
 [1];  [1];  [2];  [2]
  1. Lehigh Univ., Bethlehem, PA (United States)
  2. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

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. Generally, 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 noninductive current fraction during the ramp-up phase for NSTX-U. Simulation studies towards the achievement of noninductive ramp-up in NSTX-U have already been carried out with the TRANSP code. The optimization-based approach presented in this work is used to maximize the noninductive 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.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Lehigh Univ., Bethlehem, PA (United States); General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Grant/Contract Number:
SC0010661; FC02-04ER54698
OSTI ID:
1508622
Journal Information:
Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: A Vol. 146; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

Similar Records

TRANSP-based Optimization Towards Tokamak Scenario Development
Dataset · Mon Apr 01 00:00:00 EDT 2019 · OSTI ID:1562098

TRANSP-based closed-loop simulations of current profile optimal regulation in NSTX-Upgrade
Dataset · Thu Feb 28 23:00:00 EST 2019 · OSTI ID:1562086

TRANSP-based closed-loop simulations of current profile optimal regulation in NSTX-Upgrade
Journal Article · Mon Feb 18 23:00:00 EST 2019 · Fusion Engineering and Design · OSTI ID:1503680