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RISProbabilistic Structural Integrity Analysis of Reactor Pressure Vessels During Pressurized Thermal Shock Events
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: To apply a probabilistic fracture mechanics (PFM) analysis to the structural integrity assessment of a reactor pressure vessel (RPV), a PFM analysis code has been developed at JAEA. Using this PFM analysis code, pascal ...
Effect of Partial Welding on the Residual Stress and Structural Integrity of Piping Welds
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: When weld defects are observed during an inspection after welding, repair welding is performed after removing the defects. However, partial repair welding can potentially complicate the weld residual stress distribution. ...
Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Nowadays, it has been recognized that probabilistic fracture mechanics (PFM) is a promising methodology in structural integrity assessments of aged pressure boundary components of nuclear power plants, because it can ...
Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Structural integrity assessment of reactor pressure vessel (RPV) is important for the safe operation of nuclear power plant. For an RPV in a pressurized water reactor (PWR), pressurized thermal shock (PTS) resulted from ...