Accurate quantification of uncertainty present in the HPGe detector efficiency is very essential as uncertainty in the detector efficiency affects the measured cross-section value of neutron reaction. Error propagation has been active area of research interest in the nuclear field, since cross-section plays a major role in the nuclear reactor calculations. Therefore, Uncertainty quantification in the detector efficiency has been performed using non linear Unscented Transformation techniques such as Extended Unscented Transformation, Spherical Unscented Transformation, and Simplex Unscented Transformation. To evaluate the performance of these techniques in error propagation, a comparative study has been carried out in comparison with the well-known Monte Carlo method using the chi-square test.