[en] The analysis is presented of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch (PCM) Test Series. The test objective was to evaluate the behavior of a single pressurized water reactor (PWR) type fuel rod subjected to film boiling operation at high power following rod failure. The failure mechanisms and subsequent breakup of the fuel and cladding are discussed. The fuel rod cladding temperature profile is determined by metallographic examination of cladding microstructures and calculations based on kinetic correlations of the cladding external surface reaction layers with the duration of film boiling. Cladding-coolant and cladding-fuel interactions are investigated by metallographic and microprobe examination and chemical analysis of the cladding. Fuel restructuring and chemical changes are also addressed