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Yumin WANG, Kai LI, Zhuo HUANG, Yiliang LIU, Shuyu DAI, Jie ZHANG, Yanqing HUANG, Xiang GU, Yihang ZHAO, Shuai XU, Erhui WANG, Dong GUO, Yuejiang SHI, Huasheng XIE, Yunfeng LIANG, Minsheng LIU, the EHL-2 Team. Predictions of H-mode access and edge pedestal instability in the EHL-2 spherical torus[J]. Plasma Science and Technology, 2025, 27(2): 024005. DOI: 10.1088/2058-6272/ad9f27
Citation: Yumin WANG, Kai LI, Zhuo HUANG, Yiliang LIU, Shuyu DAI, Jie ZHANG, Yanqing HUANG, Xiang GU, Yihang ZHAO, Shuai XU, Erhui WANG, Dong GUO, Yuejiang SHI, Huasheng XIE, Yunfeng LIANG, Minsheng LIU, the EHL-2 Team. Predictions of H-mode access and edge pedestal instability in the EHL-2 spherical torus[J]. Plasma Science and Technology, 2025, 27(2): 024005. DOI: 10.1088/2058-6272/ad9f27

Predictions of H-mode access and edge pedestal instability in the EHL-2 spherical torus

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  • Author Bio:

    Yumin WANG: wangyuminb@enn.cn

  • Corresponding author:

    Yumin WANG, wangyuminb@enn.cn

  • Received Date: September 30, 2024
  • Revised Date: December 12, 2024
  • Accepted Date: December 12, 2024
  • Available Online: December 14, 2024
  • Published Date: February 11, 2025
  • The EHL-2 spherical torus is designed to demonstrate proton-boron (p-11B) fusion within a compact spherical tokamak. Its planned heating system includes a negative ion-based neutral beam injection (N-NBI), two positive ion-based NBI systems (P-NBI), electron cyclotron resonance heating (ECRH), ion cyclotron resonance heating (ICRH), and high harmonic fast wave (HHFW), with a total power output of 31 MW. According to scaling law estimates, the device is capable of achieving H-mode operation. The plasma density, ne,min, at the minimum L-H power threshold, PLH, is estimated to be 4.4×1019 m3. The pedestal parameters were calculated using the REPED model. Assuming B as the primary impurity ion, the predicted pedestal width and height are lower compared to the typical case with carbon impurities. The pedestal collisionality for EHL-2 is estimated to range between 0.06 and 0.17, indicating the potential for significant energy loss due to edge localized modes (ELMs). The heat flux on the divertor plate has been calculated using the JOREK code. The peak heat fluxes during ELM bursts are approximately 31.0 MW/m2 at the lower inboard target and 39.5 MW/m2 at the lower outboard target. A preliminary design of the resonant magnetic perturbation (RMP) coils has been completed to both control type-I ELMs and correct error fields. The system comprises 16 coils arranged into 2×4 pairs. In ELM control mode, a 14/2 component is generated at 1.7 G/kAt, with a current of 4.9 kA required to achieve σChirikov=1 at the resonant surface, where the normalized poloidal magnetic flux is 0.85. In error field (EF) modulation mode, 2/1 and 3/1 components are generated at 3.5 G/kAt and 2.8 G/kAt, respectively.

  • This work was performed under the auspices of National Natural Science Foundations of China (Nos. 12075284 and 12205157). This work was supported by the High-End Talents Program of Hebei Province, Innovative Approaches towards Development of Carbon-Free Clean Fusion Energy (No. 2021HBQZYCSB006).

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