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LICENSING AND SAFETY ANALYSIS BACKGROUND
PWR SYSTEMS TRANSIENT ANALYSIS
PWR SMALL BREAK LOCA
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accident approximately ATWS events auxiliary feedwater boiling break flow bubble BWR designs bypass calculated coarse noding cold leg condensation containment control rod control system core cooling core power core uncovery decay heat decrease depressurization discharge downcomer drywell energy enthalpy equations failure feedwater flow FIGURE flow rate flowrate fluid flux fuel rod heat removal heat transfer heatup high pressure hot leg increase initial inventory isolation valves liquid loop seal Loss-of-Coolant Accident main feedwater natural circulation neutron Nuclear parameters plant PORV pressure safety pressure suppression primary pressure primary system psia RCPs RCS pressure reactivity feedback reactor core reactor trip reactor vessel RELAP5 relief valves ruptured steam safety injection safety valves scram secondary side secondary system setpoint small break LOCA steam flow steam generator tubes steam line break subcooled suppression pool system pressure thermal hydraulic transient turbine trip two-phase vapor void fraction volume water level