A review of the development of nuclear fuel performance analysis and codes for PWRs.

• Detailed description on the governing equations and key physical phenomena in the fuel pellet and cladding are summarized. • Mature and next generation fuel performance analysis codes are concluded. • Multi-physic coupled analysis codes are focused for the fuel performance analysis. • Especially, the physical process and key phenomena are concluded during LOCA, RIA and severe accidents. 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. [ABSTRACT FROM AUTHOR]