Verification of the EUREKA-ATR Code Analysis of the SPERT-III E-core experiment

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EUREKA-ATR, a coupled nuclear thermal hydrodynamic multi-dimensional kinetic code, was adapted for the testing of models and methods. Code evaluations were made with the reactivity insertion experiments of the SPERT-IIIE-core, a slightly enriched oxide core. The code was tested for non-damaging power excursions including a wide range of initial operating conditions, such as cold-startup, hot-startup and operating-power initial conditions. Comparisons resulted in a good agreement between calculated and experimental power, energy, reactivity and clad surface temperature.