Transport analysis of the EHL-2 spherical torus in a high-ion-temperature scenario
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Xueyun Wang,
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Wenjun Liu,
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Danke Yang,
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Guang Yang,
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Muzhi Tan,
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xinchen Jiang,
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Huasheng Xie,
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Yuejiang Shi,
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Hanyue Zhao,
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Yumin Wang,
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Yunfeng Liang,
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Jiaqi Dong,
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Bin Wu,
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Chengyue Liu
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Graphical Abstract
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Abstract
EHL-2 is an ENN second-generation device aiming at studying p-B fusion reactions in a spherical torus. The design parameters are T<sub>i0</sub>~30keV, T<sub>i</sub>/T<sub>e</sub>>2, n<sub>e0</sub>~1e20m<sup>-3</sup>, I<sub>p</sub>~3MA, B<sub>t</sub>~3T, τ<sub>E</sub>~0.5s. High-ion-temperature scenario is one of the standard operation scenarios of EHL-2, aiming to reduce bremsstrahlung radiation while enhancing plasma parameters by elevating the ion to electron temperature ratio. In order to achieve high ion temperature, neutral beam injection is considered as the primary heating method during the flat-top phase. The neutral beam system for EHL-2 comprises 3-5 beams with energy/power ranging from 60 keV/4 MW, 80-100 keV/10 MW, to 200 keV/3 MW. This work conducts predictive analysis on core transport during the flat-top phase of EHL-2's high-ion-temperature scenario utilizing ASTRA. The study delineates the potential operating range of core temperature and other parameters given the designed heating capacity. Specifically, the study presents predictive simulations based on CDBM, GLF23, Bohm-gyro-Bohm and IFSPPPL transport models, evaluating the steady-state power balance, energy confinement time, and the impact of various parameters such as plasma density and NBI power on core ion temperature. The simulations demonstrate that, although sensitive to varying transport models, the design parameters of the EHL-2 high-T<sub>i</sub> scenario are hopefully attainable as long as adequate ion heating and controlled ion transport levels are ensured.
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