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Thermal Hydraulic Analysis of Core Flow Bypass in a Typical Research Reactor
Said M.A. Ibrahim,Salah El-Din El-Morshedy,Abdelfatah Abdelmaksoud 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.1
The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe conditionwith enough safety margins during normal operation and anticipated operational occurrences. In thisresearch, core flow bypass is studied under the conditions of the unavailability of safety systems. As corebypass occurs, the core flow rate is assumed to decrease exponentially with a time constant of 25 s tonew steady state values of 20, 40, 60, and 80% of the nominal core flow rate. The thermal hydraulic codePARET is used through these calculations. Reactor thermal hydraulic stability is reported for all cases ofcore flow bypass.