In order to better evaluate the heat transfer models of the domestic autonomous pressurized water reactor (PWR) subchannel analysis software, the heat transfer models of several domestic autonomous PWR subchannel analysis software under review by the National Nuclear Safety Administration were evaluated and studied. Firstly, it was confirmed that the practical significance of the heat transfer model for the autonomous PWR subchannel analysis software was that the relevant parameters calculated by the software heat transfer model were mainly reflected in the closure process of the liquid phase energy conservation equation. Then, through the experimental confirmation and sensitivity analysis of the onset of nucleate boiling (ONB) model, it was finally obtained that the calculation deviation of the ONB model had little effect on the calculation results of the parameters such as the axial pressure in the channel and the outer wall temperature of the fuel cladding. Although the calculation deviation of ONB model may have a certain impact on the void fraction and departure from nucleate boiling ratio(DNBR) in the channel, it is limited to the position near the starting point of ONB, and has little impact on the parameter calculation of subsequent axial position with higher void fraction and smaller DNBR in the channel.