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.