Detection and Mode Identification of Axial Cracks in the Steam Generator Tube of the Nuclear Power Plant Using Ultrasonic Guided Wave

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概要

• 論文の詳細を見る
• 2010-08-01

著者

• YOON Byungsik

  Korea Electric Power Research Institute

• YANG Seunghan

  Korea Electric Power Research Institute

• LEE Heejong

  Korea Electric Power Research Institute

• KIM Yongsik

  Korea Electric Power Research Institute

関連論文

• Detection and Mode Identification of Axial Cracks in the Steam Generator Tube of the Nuclear Power Plant Using Ultrasonic Guided Wave
• Detection and Mode Identification of Axial Cracks in the Steam Generator Tube of the Nuclear Power Plant Using Ultrasonic Guided Wave
• Parameter Study for the Evaluation of Crack Depth in Steam Generator Tubing
• Development of an Ultrasonic Performance Demonstration System for Dissimilar Metal Welds in Korean Nuclear Power Plants
• Development of an Ultrasonic Performance Demonstration System for Dissimilar Metal Welds in Korean Nuclear Power Plants
• An experimental result on flaw sizing of steam generator tube at nuclear power plants using ultrasonic testing
• An experimental result on flaw sizing of steam generator tube at nuclear power plants using ultrasonic testing

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