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RISThermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The reactor channel of the horizontal core of pressurized heavy water reactors experiences very low sustained flow during loss of coolant accident (LOCA) at the reactor inlet feeders caused by ...
Assessment of the Code “PTCREEP ” for IPHWR Pressure Tube Ballooning Study
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In Indian pressurized heavy water reactor (PHWR), loss of coolant accident with simultaneous failure of emergency core cooling system can lead to significant temperature rise in the pressure ...