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Published on: August 25, 2016
"Snowflake" H mode in a tokamak plasma
1Ecole Polytechnique Fédérale de Lausanne, Centre de Recherches en Physique des Plasmas, Association Euratom-Confédération Suisse, Station 13, CH-1015 Lausanne, Switzerland. francesco.piras@epfl.ch
Researchers achieved a stable edge-localized mode (ELM) H-mode using a novel snowflake divertor in the TCV tokamak. This new configuration significantly reduces ELM frequency and enhances energy confinement compared to standard H-mode operations.
Area of Science:
- Plasma Physics
- Fusion Energy Research
- Tokamak Operations
Background:
- Edge-localized modes (ELMs) are crucial for tokamak performance but can disrupt plasma stability.
- The H-mode regime offers improved confinement but requires careful control of edge plasma conditions.
- Divertor configurations play a key role in managing heat and particle exhaust in fusion devices.
Purpose of the Study:
- To establish and investigate an edge-localized mode (ELM) H-mode regime in a novel "snowflake" divertor configuration.
- To compare the ELM characteristics and stability of the snowflake divertor regime with conventional single-null diverted H-mode.
- To experimentally validate the power redistribution capabilities of the snowflake divertor.
Main Methods:
- Successful establishment of ELM H-mode using electron cyclotron heating in a TCV tokamak snowflake divertor.
- Comparative analysis of ELM frequency and normalized ELM energy between snowflake and conventional single-null diverted H-mode.
- Experimental confirmation of power redistribution to additional strike points in the snowflake configuration.
Main Results:
- The snowflake divertor regime demonstrated 2-3 times lower ELM frequency compared to conventional H-mode.
- A 20%-30% increase in normalized ELM energy (ΔWELM/Wp) was observed in the snowflake regime.
- Enhanced stability of mid- to high-toroidal-mode-number ideal modes was consistent with snowflake ELM phenomenology.
Conclusions:
- The snowflake divertor configuration offers a promising pathway for improved ELM control and enhanced plasma stability in tokamaks.
- This configuration facilitates effective redistribution of edge power, mitigating heat loads on divertor components.
- The findings represent a significant advancement in optimizing tokamak operational regimes for future fusion reactors.
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