Plasma rotation and its shear are key parameters influencing the performance of fusion devices. The prediction and control of plasma rotation velocity are of great significance for improving the stable operation and confinement of future fusion reactors. External momentum injection methods are insufficient to suppress resistive wall mode instability while achieving Q greater than 5 in international thermonuclear experimental reactor (ITER). Therefore, it is necessary to conduct experimental research on intrinsic plasma rotation that does not rely on external momentum injection. To better predict the magnitude of intrinsic rotation velocity in future fusion devices, we conduct an experimental study on the scaling of residual stress and dimensionless parameters on EAST. Using the balanced neutral beam, multiple measurements of intrinsic torque are performed, providing experimental basis for predicting the intrinsic rotation in future tokamak devices. The scaling results indicate that the core residual stress is dependent on $\rho_{\ast}^{-1.80\pm1.26}$, while the scaling of edge residual stress shows an opposite trend with $\rho _{\ast }^{1.26\pm0.63}$. This suggests that as the device size increases, the core residual stress in future large devices can increase, while the edge residual stress can decrease. The difference in scaling results between the core and edge residual stress indicates that in the edge region, the symmetry-breaking mechanism other than $\boldsymbol{E}\times\boldsymbol{B}$ flow shear dominates the generation of residual stress in the scrape-off layer. A relationship is found between intrinsic torque and $\nu _{\ast }$, revealing that the core intrinsic torque depends on $\nu _{\ast }^{-0.21\pm0.18}$. Combining the scaling results of core intrinsic torque with the gyroradius and normalized collisionality, the scaling law for core intrinsic torque is obtained to be $\rho _{\ast }^{-1.39\pm0.71}\nu _{\ast }^{0.11\pm0.10}$. Using plasma parameters of ITER operation scenario 1, the core intrinsic torque in future ITER plasma is predicted to be $(1.0\pm6.3)~{\mathrm{N}}{\cdot} {\mathrm{m}}$, which is much smaller than the predicted magnitude at DIII-D.