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U PWR Experience in Operational Transients
k Analysis of Incomplete Control Rod Insertion
35 other sections not shown
accident AEOD assessment ATWS auxiliary feedwater boiling water reactor calculated caused cold leg component condensation control room cooldown cooling core damage core melt frequency decay heat downcomer Electric EPRI evaluation failure feedwater pump fuel heat removal hot leg HPCI improved incidents initiated INPO loop LOSP loss of offsite main feedwater natural circulation nuclear power plants Nuclear Regulatory Commission occurred offsite power operating experience operational transients operator actions parameters performed plant data plant transients PORV pressurized water reactors primary system Probabilistic Risk Assessment problems procedures pump trip RCIC RCPs reactor coolant pumps reactor trip reactor vessel Regulatory RELAP5 relief valve RETRAN risk safety injection scram SEE-IN sequence shutdown signal significant simulation small break station blackout steam generator tube steam line Taipower temperature thermal thermal-hydraulic tion tube rupture turbine trip units utilities