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Published on: May 10, 2021
Millimeter-wave high-wavenumber scattering diagnostic developments on EAST and NSTX-U
Pengjun Sun1, Xianzi Liu2, Yang Ren3
1Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui 230031, China.
A new 4-channel, high-k poloidal scattering system for the Experimental Advanced Superconducting Tokamak (EAST) will measure electron density fluctuations. This system aids in studying plasma instabilities like the electron temperature gradient (ETG) mode.
Area of Science:
- Plasma Physics
- Fusion Energy Research
- Diagnostic Development
Background:
- The Experimental Advanced Superconducting Tokamak (EAST) requires advanced diagnostics to study plasma behavior.
- Understanding high-k electron density fluctuations is crucial for controlling plasma instabilities in fusion devices.
- Existing diagnostic capabilities may be limited in probing small-scale turbulence.
Purpose of the Study:
- To develop and implement a novel 4-channel, high-k poloidal millimeter-wave collective scattering system for EAST.
- To measure high-k electron density fluctuations and their poloidal wavenumber spectrum (kθ).
- To investigate ion and electron-scale plasma instabilities, including the electron temperature gradient (ETG) mode.
Main Methods:
- Deployment of a 270 GHz mm-wave probe beam across specific ports on the EAST tokamak.
- Utilizing large aperture optics to capture scattered radiation at four simultaneous angles.
- Development of beam tracing and data interpretation modules tailored for high-k scattering diagnostics.
Main Results:
- Successful development and laboratory testing of the 4-channel, high-k poloidal scattering system.
- The system is designed to measure poloidal wavenumbers up to 20 cm-1.
- Installation on EAST is currently underway, enabling in-situ measurements.
Conclusions:
- The new high-k scattering system significantly enhances EAST's capability to probe small-scale electron density fluctuations.
- This diagnostic advancement will provide crucial data for understanding and mitigating plasma instabilities.
- The developed modules are also applicable to other tokamak facilities like NSTX-U.
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