International Nuclear Safety Center database on thermophysical properties of reactor materials

Conference · Fri Aug 01 04:00:00 EDT 1997

OSTI ID:541879

Fink, J K; Sofu, T; Ley, H

The International Nuclear Safety Center (INSC) database has been established at Argonne National Laboratory to provide easily accessible data and information necessary to perform nuclear safety analyses and to promote international collaboration through the exchange of nuclear safety information. The INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor material properties for normal operating conditions, transients, and severe accidents. The initial focus of the database is on thermodynamic and transport properties of materials for water reactors. Materials that are being included in the database are fuel, absorbers, cladding, structural materials, coolant, and liquid mixtures of combinations of UO{sub 2}, ZrO{sub 2}, Zr, stainless steel, absorber materials, and concrete. For each property, the database includes: (1) a summary of recommended equations with uncertainties; (2) a detailed data assessment giving the basis for the recommendations, comparisons with experimental data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equations; and (4) property values tabulated as a function of temperature.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 541879
• Report Number(s): ANL/RE/CP--91778; CONF-970629--; ON: DE97053026
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS
COOLANTS
FUEL CANS
INFORMATION SYSTEMS
NEUTRON ABSORBERS
NUCLEAR FUELS
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR MATERIALS
THERMODYNAMIC PROPERTIES
URANIUM OXIDES
WATER COOLED REACTORS
ZIRCONIUM OXIDES