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Author(s) |
Singh, A. R.; Tariq, A.; Sahoo, P. K.; Majumdar, P.; Mukhopadhyay, D. (RSD)
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Source |
Annals of Nuclear Energy, 2021. Vol. 155: Article no. 108160 |
ABSTRACT
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Moderator acts as primary heat sink to arrest the unwarranted heat-up of fuel channels in the scenario of loss of coolant accident along with the unavailability of emergency core cooling system. In addition, severe heat-up of channel (which consists of fuel bundles, Pressure Tube, PT and Calandria Tube, CT) also occurs during any un-called for event of moderator-cooling/make-up system malfunctioning. Eventually, this all lead to the major loss in structural rigidity. Present investigation is performed to study the sagging deformation of PT for standardized 220MWe Indian PHWR. A scaled-down PT (1/3rd scale) is tested with a uniquely designed experimental setup that is capable of capturing high temperature sagging behavior. Results confirm that the Indian PT significantly deforms under thermally assisted ratedependent plasticity (creep) above 600 oC. Post-test visual examination reveals no cracks in the PT, however a significant thinning of the PT near the junction of weight simulators is observed. |
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