Piping cracks in JPDR. I. Relation between crack and stress.:Relation between Crack and Stress

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概要

• 論文の詳細を見る

• In JPDR, primary coolant leaked in August 1972 through a crack in the heat affected zone between nozzle safe end of pressure vessel and pipe. And other piping systems were then investigated, and cracks were detected in two systems. Then relations between stress and cracks in the pipes were studied. Stress was analyzed by elastic theory and examined by mockup fatigue test of pipe. Initiation of cracks are not caused by stress alone, indicating the existence of other factor involved.

• 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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