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Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents
The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date:
December 16, 1960
Creator:
Pierce, R. M.
System:
The UNT Digital Library