Abstract
This paper describes the results of in-pile experiments and analyses to study the influence of waterlogged fuel rod rupture to the adjacent fuel rods and channel box under reactivity initiated accident (RIA) conditions. A single waterlogged fuel rod surrounded by intact fuel rods m a flow shroud was irradiated by a large neutron pulse in the Nuclear Safety Research Reactor (NSRR) to simulate a prompt power excursion of RIA'S. It was found that the pressure pulse generated at the rupture of waterlogged fuel rod had little mechanical influence on the adjacent fuel rods, but caused the ballooning of the flow shroud which included a rupture rod. The exclusion of coolant due to evaporation near the rupture region degraded the cooling of adjacent fuel rods and reduced the failure threshold. A 2-D analysis by STEALTH-J code revealed that a channel box of a BWR might be deformed by the pressure pulse to occupy the control rod path when a waterlogged fuel rod contained in a channel box ruptured In an RIA.
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