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 ...

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. ...

Abstract: The seismic design review guide in Japan was revised in September 2006 to address the occurrence of a large earthquake beyond the design basis. In addition, Japanese nuclear power plants (NPPs) experienced multiple large ...

Abstract: In this study, the residual stresses generated within the overlaywelded cladding and base material of reactor pressure vessel (RPV) steel were measured for aswelded and postwelded heattreated conditions using the sectioning ...

Abstract: We conducted fracture toughness testing on five types of commercially manufactured steel with different ductiletobrittle transition temperatures. This was performed using specimens of different sizes and shapes, including ...

Abstract: Some Japanese nuclear power plants have experienced several large earthquakes beyond the design basis ground motion. In addition, cracks resulting from long-term operation have been detected in piping systems. Therefore, ...