Piping cracks in JPDR. II. In service inspection of weld joints in reactor coolant pressure boundary.:In Service Inspection of Weld Joints in Reactor Coolant Pressure Boundary

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概要

• 論文の詳細を見る

• Ultrasonic and radiographic examinations of weldments in the primary piping of the Japan Power Demonstration Reactor (JPDR) revealed crack indications in two reactor vessel nozzle safe-end to pipe joints CS-1 and UL-1, while on the joint FW-132 a crack-like indication was given only on the ultrasonic record.<BR>These three parts of the reactor piping were removed from the reactor, and subjected to thorough nondestructive and destructive examination in laboratory.<BR>The indications obtained in the field by ultrasonic and radiographic means agreed with each other, and were further confirmed by the laboratory tests.<BR>Crack indications given by one nondestructive method and not concurred by another method may safely be taken as inconsequential on spurious.

• 一般社団法人 日本原子力学会の論文

著者

• Torikai Kinichi

  Japan Atomic Energy Research Institute

• FUTAMURA Yoshiaki

  Japan Atomic Energy Research Institute

• KINOSHITA Takehiko

  Japan Atomic Energy Research Institute

関連論文

• Variation by Time in Boiling Heat Transfer Caused by Generation of Bubbles
• Piping cracks in JPDR. IV. Analysis of cause of cracks found near weld joints connecting reactor vessel nozzle safe-end to pipe.:Analysis of Cause of Cracks Found near Weld Joints Connecting Reactor Vessel Nozzle Safe-End to Pipe
• Piping cracks in JPDR. I. Relation between crack and stress.:Relation between Crack and Stress
• Piping cracks in JPDR. II. In service inspection of weld joints in reactor coolant pressure boundary.:In Service Inspection of Weld Joints in Reactor Coolant Pressure Boundary
• The Contact Area of Boiling Bubbles on the Heating Surface

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