Nuclear fuel performance analysis is fundamental for the design of pressurized water reactors (PWRs) with great safety concerns. The analysis of a fuel rod involves many complex processes, including heat transfer, mechanics, material, mass transfer and chemistry interaction. This paper reviews the basic frame and recent progress of fuel performance analysis of PWRs during normal operation and accidents. Three conservation governing equations of heat, momentum and mass transfer, and the solution strategies are mentioned first. Reviewed phenomena include gas gap heat transfer, fission gas release, fuel pellet relocation, pellet cladding mechanical and chemical interactions, waterside corrosion, etc. Tools used to execute the performance analysis, namely, fuel performance analysis codes, are divided into mature and next generation codes and typical codes are also reviewed. FRAPCON/FRAPTRAN and FROBA are introduced as two representatives of mature generation codes, and BISON, ALCYONE and CAMPUS are reviewed as the representatives of the developing generation codes. The fuel performance analysis in design-basis and severe accidents are also extensively reviewed as a new developing topic of fuel performance analysis, particularly in severe accidents.

核燃料性能分析是设计具有重大安全问题的压水反应堆 (PWR) 的基础。燃料棒的分析涉及许多复杂的过程，包括传热、力学、材料、传质和化学相互作用。本文综述了压水堆正常运行和事故时燃料性能分析的基本框架和最新进展。首先提到热、动量和质量传递的三个守恒控制方程和求解策略。审查的现象包括气隙传热、裂变气体释放、燃料芯块重新定位、芯块包壳机械和化学相互作用、水侧腐蚀等。 用于执行性能分析的工具，即燃料性能分析代码，分为成熟代码和下一代代码，并对典型代码进行了回顾。FRAPCON/FRAPTRAN和FROBA作为成熟代码的两个代表被介绍，BISON、ALCYONE和CAMPUS作为发展代码的代表被审查。设计基准和严重事故中的燃料性能分析也被广泛审查为燃料性能分析的一个新发展课题，特别是在严重事故中。