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A series of reactor frequency response measurements, relating flux or power level to a reactivity input function, were made to evaluate reactor stability for different values of power parameters. These parameters included: power level, steam pressure, and control rod position. The results were extrapolated to predict EBWR stability at higher operating powers. The experimental data may also be used to evaluate the thermodynamic and hydraulic constants.

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No abstract

Styrofoam was used successfully as a void material in the representation of hot reactor conditions during the EBWR zero power experiments = The void requirements were determined from available heat transfer data and then Styrofoam strips were designed and manufactured by special equipment. These strips were inserted in the fuelelement water channels and the reactivity changes noted. The data were then converted to boiling and temperature coefficients. The nuclear properties of the material were excellent, and its use proved economical. The experimental accuracy was good, but probably could be improved by sealing the surface of the material against water absorption.