New HL2M tokamak operation foreseeing to support the next step fusion energy research

New tokamak HL-2M (Ip=2.5~3MA, B=2.2T, R=1.78m, a=0.65m) is dedicated to address both the plasma physics and technology issues in ITER and future fusion reactors. First plasma has generated in 2020. A combination of the flexible magnet coil system and the heating power of 27 MW (15MW NBI, 8MW ECRF, 4MW LHCD) allows HL-2M to be an excellent platform for tests and qualification of various advanced divertor concepts (such as snowflakes, tripod) and high heat flux plasma facing components. Heat flux on the divertor target could reach 10~20MW/m². Scenarios, such as inductive, hybrid and full non-inductive regimes, achieved via various auxiliary heating combinations. Present paper reports the key performance foreseeing during HL-2M operation, including divertor heat and particle flux, as well as various operation scenarios. In the inductive regime with high plasma current (2.5MA/2.2T), the central plasma temperature can reach up to ~10 keV at density of . Hybrid scenarios, with bootstrap current f_BS=30%~50%, can reach in plasma current I_p =1.0~1.4MA, Greenwald fraction f_G ~0.5 by combining NBCD with ECCD or ECCD+LHCD. Full non-inductive regimes, such as the hybrid steady state regime and the regime with a reversed magnetic shear, can reach in I_p=1MA with f_BS>60%, H_98(y,2) ~1.3, β_N >3. Therefore, HL-2M can provide scientific and technical solutions of the divertor and the operation issues for ITER, especially in its pre-fusion power operation phase.