Modeling of cladding and fuel motion in a loss of flow situation for GCFR safety analysis. Progress report 6, October 15, 1975--January 15, 1976 (open access)

Modeling of cladding and fuel motion in a loss of flow situation for GCFR safety analysis. Progress report 6, October 15, 1975--January 15, 1976

The first experiments have been run using electrically heated, simulated fuel elements in an inert gas (argon) loop. The fuel elements have a chopped cosine power input and have a Pb/Sn alloy cladding. Single elements were used in the first two experiments with a step power pulse of about 1 kW/ft which was sufficient to melt the center of the clad within 8 to 10 sec. As the molten cladding entered the blanket (unheated) region, it froze within about 1 inch. The apparatus for the stainless steel pouring experiment is progressing. Additional models for freezing of molten cladding in colder regions are being analyzed and tested against the single tube pouring tests previously reported. Analytical routines are under development.
Date: February 15, 1976
Creator: Eggen, D. T.
System: The UNT Digital Library
Nuclear safety characterization of sodium fires and fast reactor fission products. Quarterly technical progress report, October--December 1975 (open access)

Nuclear safety characterization of sodium fires and fast reactor fission products. Quarterly technical progress report, October--December 1975

Progress is summarized in the areas of SOMIX code development, simulated fuel element source term studies, aerosol leakage tests and calculations, fuel and fission product release from burning sodium, aerosol source term from vaporized fuel properties of high temperature fuel mixtures, and aerosol source from MCFI.
Date: February 15, 1976
Creator: unknown
System: The UNT Digital Library