Fuels discharged from the KORI-1 nuclear power plant have been subjected to hot-cell examination at the post-irradiation examination facility of the Korea Atomic Energy Research Institute. The main objectives were to increase the technical depth of the post-irradiation examination (PIE) and evaluation, and to prepare systemic data base of the irradiation behavior for pressurized water reactor fuels. The examination items include a visual inspection, a dimensional measurement, and a gamma-scanning for the fuel assembly in pool. The hot-cell examination items for the fuel rod are a visual inspection, a profilometry, an axial gamma-scanning, an eddy current testing, a X-ray radiography, a fission gas collection, and its chemical composition analysis, a metallography, a ceramography, a micro gamma-scanning, a densimetry, and a burnup measurement by the chemical analysis method. The in-core fuel behavior parameters, such as a fuel rod/stack length change, a rod internal pressure change, a fission gas release rate, a cladding corrosion, fuel rod creep and growth, and a burnup, have been determined experimentally and compared with the predicted values by means of computer codes. It is appeared that the predicted values are well agreeable with the experimental results, except that for the fuel rod growth. (Author).