International Nuclear Safety Center database on thermophysical properties of reactor materials

The International Nuclear Safety Center (INSC) database has been establishe d at Argonne National Laboratory to provide easily accessible data and info rmation necessary to perform nuclear safety analyses and to promote interna tional collaboration through the exchange of nuclear safety information. Th e INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor-material propertie s for normal operating conditions, transients, and severe accidents. The in itial focus of the database is on thermodynamic and transport proper ties o f materials for water reactors. Materials that are being included in the da tabase are fuel, absorbers, cladding, structural materials, coolants, and l iquid mixtures of combinations of UO2, ZrO2, Zr, stainless steel, absorber materials, and concrete. For each property, the database includes (1) a sum mary of recommended equations with uncertainties; (2) a detailed data asses sment giving the basis for the recommendations, comparisons with experiment al data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equati ons; and (4) property values tabulated as a function of temperature.