RECOMMENDED PROPERTY AND REACTION KINETICS DATA FOR USE IN EVALUATING A LIGHT-WATER-COOLED REACTOR LOSS-OF-COOLANT INCIDENT INVOLVING ZIRCALOY-4- OR 304-SS-CLAD UO{sub 2}

摘要

Selected values are presented for the high temperature physical and mechanical properties of fuel element materials involved in a loss-of-coolant incident in a boiling water or pressurized water nuclear reactor. The fuel element materials considered are Zircaloy-2 and -4, 304 SS, and UO{sub 2}. Where possible, the property values have been critically evaluated taking into consideration the meltdown environment of steam or steam and air. The physical properties discussed are: melting point, boiling point, heat of fusion, heat of vaporization, vapor pressure, phase transformations, coefficient of thermal expansion, density, total normal emittance, thermal conductivity and enthalpy and heat capacity. The mechanical properties discussed are: tensile strength, ductility, compressive strength, and modulus of elasticity. In most instances, values of various properties are given as a function of temperature to the melting point of the material. The kinetics of the oxidation reactions fo the cladding materials with steam are also discussed and equations presented for calculation of oxidation rates under isothermal conditions for one atmosphere of steam. (auth)