OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1978 · 12 citations · 0 references
EngineeringOctavia Computer CodePressure VesselVessel Failure PressuresProcess SafetyReliability EngineeringFailure AnalysisSystems EngineeringPressurized Water ReactorsModeling And SimulationNuclear ReactorsReliabilityComputer EngineeringCaused Pressure TransientsEngineering Failure AnalysisNuclear EngineeringCivil EngineeringNuclear SafetyReactor Safety
The OCTAVIA computer code has been developed to calculate the probability of pressure vessel failure from operationally caused pressure-transients which can occur in pressurized water reactors. The analysis approach involves calculation of vessel failure pressures using fracture mechanics methods and estimation of pressure-transient characteristics using historical nuclear data. Any of the parameters in the code can be modified for sensitivity analyses. The Surry 1 pressure vessel is analyzed as an example problem to demonstrate the code's capabilities.