Recent experiments on the spherical tokamak has discovered the conditions to create a powerful plasma, easy shaping and amplification of tability, high bootstrap current and confinement Energy. The spherical torus (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as ITER as it focuses toward the compact Component Test Facility (CTF) and higher toroidal beta regimes to improve the design of DEMO and a Power Plant. To support the ST development path, one option of a Next Step Spherical Torus (T) device is examined. T is a “performance extension” (PE) stage ST with a plasma current of 5 - 10 MA, R = 1.5, BT ? 2.7 T with flexible physics. The baseline heating and current drive system for T is the 30 MW NBI system and a 10 MW of ion cyclotron range of frequency (ICRF) and high harmonic fast wave (HHFW) system. Here we investigated lower hybrid wave interactions in the T reactor And found an optimal lower hybrid wave power and frequency for it. Finally, we compared the lower hybrid waves optimal conditio T, NSTX spherical tokamak and TFTR tokamak torus. Our results indicate that the use of lower hybrid waves in improved spherical tokamak T compared to the spherical tokamak generation is much better and more efficient. Also comparison of the T tokamak and TFTR torus tokamak shows that both have been able to create a high driving current. And even the ability of lower hybrid wave to reach to the center of the plasma is improved for T reactor. Keywords: Spherical Tokamak, Lower hybrid Wave, Heating, Current drive