Control of the Plasma-Material Interface for Long Pulse Optimization in the Experimental Advanced Superconducting Tokamak
Lead PI:
Rajesh Maingi, Princeton Plasma Physics Laboratory
Institutional PIs:
John Canik, Oak Ridge National Laboratory
Brian Wirth, University of Tennessee at Knoxville
Daniel Andruczyk, University of Illinois at Urbana-Champaign
Graham Wright, Massachusetts Institute of Technology
Kevin Tritz, Johns Hopkins University
Zhehui Wang, Los Alamos National Laboratory
The aim of this project is to understand and control the plasma-material interface to improve long pulse discharge control and performance in the Experimental Advanced Superconducting Tokamak (EAST) device, emphasizing the unique strength of this facility. A multi-institutional team consisting of national labs and universities will conduct the collaborative research.
The focus of this project is on long pulse recycling control and optimization, which requires optimization because of the broad range of materials used for plasma-facing components (PFC) and wall conditioning techniques in EAST. EAST uses both lithium deposition and cryogenic condensation pumps for control of plasma recycling from the PFCs during long pulse discharges. The research elements include:
- Evaluate the performance of the different PFC materials, which include tungsten, molybdenum, and graphite, and the role of lithium wall conditioning, including determination of the minimal usage for acceptable performance; optimize lithium delivery tools
- Analyze the roles of the lithium and the divertor cryopump in long pulse recycling and density control, and provide a physics-based re-design of the lower divertor plenum to optimize cryopump particle exhaust
- Measure net erosion and material migration with the use of marker tiles, and enhanced impurity density diagnostics
Because long pulse recycling control is needed for next step devices, the knowledge will be used to improve reactor designs, while also advancing the EAST program.