Poloidal field system and advanced divertor equilibrium configuration design of the EHL-2 spherical torus

作者：Xiang Gu, G. George Yin, Yuejiang Shi, Lili Dong, Yu Wang, Hong Zang, Yuanming 圆明 YANG 杨, Huasheng 华生 XIE 谢, Jiaqi 家齐 DONG 董, Yueng-Kay Martin 元凯 PENG 彭, Baoshan 保山 YUAN 袁, Qingwei 青巍 YANG 杨, Yunfeng 云峰 LIANG 梁, Xianming 显明 SONG 宋, Minsheng 敏胜 LIU 刘, the EHL-2 Team · 发表于：Plasma Science and Technology · 年份：2025 · DOI：10.1088/2058-6272/adae72 · 被引用次数：10 · 研究领域：Fusion materials and technologies、Magnetic confinement fusion research、Nuclear reactor physics and engineering

Abstract The EHL-2 (ENN He-Long 2) spherical torus (ST) project focuses on advancing spherical torus technology to address the unique challenges of p- 11 B fusion, which demands significantly higher ion temperature and heat flux to the divertor plate compared to traditional deuterium-tritium fusion. With a major radius of 1.05 m and a plasma current of 3 MA, the project aims to evaluate and optimize advanced divertor configurations, specifically the Super-X and X-point target (XPT) divertors. The design incorporates an up-down double-null configuration featuring a conventional inner divertor and an XPT outer divertor to effectively reduce the heat flux. The poloidal field (PF) coil system is meticulously optimized to balance engineering constraints with the flexibility in equilibrium configurations. This design is expected to provide a reference equilibrium configuration for other physics design issues and offer critical insight into heat load management.