The damage caused by primary water stress corrosion crack (PWSCC) has been revealed in the Noz Safe-end with alloy 600 domestical ly and internationally in recent years. The guideline has been examined and studied to clarify the application of inspection tech niques and preventive maintenance method, the approach to the evaluation for acceptance level of continuous operation and inspect ion frequency. The summary of this guideline is introduced in this paper....
英字タイトル:
Summary of Guideline for Inspection and Evaluation of PWR Redactor Internal[Class 1 component Nozzle Safe-end dissimilar metal weld]

In recent years, reports have increased about failure cases caused by high cycle thermal fatigue both at light water reactors and fast breeder reactors. One of the reasons of the cases is a turbulent mixing at a Tee -junction, where hot and cold temperature fluids are mixed, in a coolant system. In order to prevent thermal fatigue failures at Tee-junctions, The Japan Society of Mechanical Engineers published the guideline which is an evaluation method of high cycle thermal fatigue damage at nuclear pipes. ...
英字タイトル:
Comparison of Evaluation Results of Piping Thermal Fatigue EvaluationMethod based on Equivalent Stress Amplitude