Abstract: The D-T plasma discharge is a critical operational mode for reactor-grade Tokamak devices. The helicon wave current drive on HL-3 Tokamak device was studied in the paper. Based on the fast wave dispersion relation under the HL-3 Tokamak device D-T discharge mode, the optimal helicon wave parameter range was obtained. Meanwhile, the wave ray trajectories, wave power deposition and the related current drive were calculated through the coupled GENRAY/CQL3D code. The results show that wave rays can penetrate directly into the core plasmas, enabling robust off-axis current drive over a broad radial region, with a current drive efficiency of 85 kA/MW and a dimensionless current drive efficiency of 0.36. Simultaneously, the presence of tritium (T) ion was proved to have little impact on the current drive. Finally, the electron phase-space distribution function was analyzed using the CQL3D code, where more captured particles were converted into passing particles, thereby enhancing the overall plasma current drive in the device. These findings highlight the promising potential of helicon waves for application in the HL-3 Tokamak device. The HL-3 device has achieved significant experimental progress in areas such as plasma operation at high beta and mega-ampere (MA) level plasma current discharges. The relatively mature lower hybrid wave (LHW) systems on the DⅢ-D and KSTAR devices are expected to play a key role in the D-T high-performance operation of the HL-3 device. Considering the HL-3 Tokamak device’s engineering design maximum of 3 MA plasma operation mode, if the bootstrap current fraction accounts for 50% and neutral beam and electron cyclotron wave heating drive 50% of the non-inductive current, a 10 MW LHW system would be sufficient to support the remaining non-inductive current demand. The findings of this study also aim to offer new approaches and insights for off-axis current drive schemes in future domestic reactor-grade Tokamak devices.