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Articles by author: Yoon Suk Chang

• A Parametric Study on the Fracture Mechanics Analysis of Elbow with Surface Crack
  Published in: Fracture and Strength of Solids IV (p505)
• Alternative Fatigue Evaluation of Nuclear Piping Designed by ANSI B31.1 Code
  Published in: Advances in Fracture and Strength (p1659)
• Application of Grid-Based Approach for Auto Mesh Generation of Vacuum Chamber
  Published in: Fracture and Strength of Solids VI (p631)
• Application of Modified Grid-Based Approach for Auto Mesh Generation of IT-Related Products
  Published in: Advanced Nondestructive Evaluation I (p12)
• Assessment of Geometry Independent Fracture Resistance Characteristics Based on Local Approach
  Published in: Advances in Fracture and Strength (p2403)
• Assessment of In-Plane Size Effect for Nuclear Carbon Steels Using Damage Models
  Published in: The Mechanical Behavior of Materials X (p1361)
• Assessment of Steam Generator Tubes with Dual Axial Through-Wall Cracks
  Published in: Safety and Structural Integrity 2006 (p71)
• Burst Pressure Estimation of Steam Generator Tubes Based on Fracture Mechanics Analyses
  Published in: Advanced Nondestructive Evaluation I (p666)
• Cleavage Fracture Evaluation Using Local Approach for SA508 Carbon Steel at -60°C
  Published in: Advances in Safety and Structural Integrity 2005 (p193)
• Development of a Neural Network-Based Real-Time Fatigue Monitoring System for the Heavy Load Carrying Facility
  Published in: Advances in Safety and Structural Integrity 2005 (p201)
• Development of an Integrity Evaluation System for Steam Generator Tubes in a Nuclear Power Plant
  Published in: Safety and Structural Integrity 2006 (p157)
• Development of Corroded Gas Pipeline Assessment Program Based on Limit Load Solution
  Published in: Advances in Fracture and Strength (p47)
• Development of Toughness Scale Diagram Considering Temperature Dependency
  Published in: The Mechanical Behavior of Materials X (p513)
• Development of Web-Based Fatigue Life Evaluation System for Reactor Pressure Vessel
  Published in: Safety and Structural Integrity 2006 (p25)
• Fatigue Life Evaluation for Nuclear Power Plant Using Green’s Function and Real Operating Histories
  Published in: Experimental Mechanics in Nano and Biotechnology (p979)