为更好地开展自主化压水堆（pressurized water reactor, PWR）子通道分析软件传热模型的评价工作，对国家核安全局目前在审的几款国产自主化压水堆子通道分析软件的传热模型开展分析研究。首先，确认传热模型对于自主化压水堆子通道分析软件的实际意义，即软件传热模型计算的相关参数主要体现在液相能量守恒方程的封闭过程中。然后通过对核态沸腾起始点（onset of nucleate boiling, ONB）模型的实验确认以及敏感性分析。最终得到ONB模型的计算偏差对通道内轴向压力、燃料包壳外壁面温度等参数的计算结果影响很小。虽然ONB模型的计算偏差会对通道内空泡份额以及偏离泡核沸腾比（departure from nucleate boiling ratio, DNBR）产生一定影响，但仅局限于ONB起始点附近位置，对后续高空泡份额、更小DNBR的通道轴向位置的参数计算影响很小。

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.