Materials Test-2 LOCA Simulation in the NRU Reactor PDF Download

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Materials Test-2 LOCA Simulation in the NRU Reactor

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Book Description
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This third experiment of the program produced fuel cladding temperatures exceeding 1033 K (1400°F) for 155 s and resulted in eight ruptured fuel rods. Experiment data and initial results are presented in the form of photographs and graphical summaries.