Won-Geun Yi

ORCID: 0000-0003-4301-3218
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About
Contact & Profiles
Research Areas
  • Erosion and Abrasive Machining
  • Welding Techniques and Residual Stresses
  • Surface Treatment and Residual Stress
  • Hydrogen embrittlement and corrosion behaviors in metals
  • High-Velocity Impact and Material Behavior
  • Engineering Applied Research
  • Non-Destructive Testing Techniques
  • Fatigue and fracture mechanics
  • Microstructure and Mechanical Properties of Steels
  • Tendon Structure and Treatment

Doosan Heavy Industries & Construction (South Korea)
2018-2022

Pukyong National University
2019

Pusan National University
2007

Laser shock peening creates compressive residual stress on the surface of material, reducing corrosion cracking and increasing fatigue life. FE simulation laser is an effective way to determine mechanical effects material. In conventional simulations peening, explicit analysis used while pressure loads are applied switched into implicit dissipate kinetic energy. this study, static damping was adopted energy without conversion analysis. Simulation a single multiple shocks performed,...

10.3390/met11101516 article EN cc-by Metals 2021-09-24

304 stainless steels with carbon contents of 0.074wt%C and 0.064wt%C were tested to investigate the effect content on intergranular corrosion in heat affected zone. Stainless two types subjected various tests identify characteristics such as nondestructive properties, mechanical chemical composition, delta ferrite content, structural observation. In ASTM A262 test for detecting attack associated chromium carbide precipitates, steel a was found be resistant corrosion, but high have zone 2 3...

10.5781/jwj.2019.37.4.6 article EN Journal of Welding and Joining 2019-07-22

Abstract Stress corrosion cracking (SCC) of nuclear power plant components is perhaps the most significant issue affecting availability and lifetime management. Actions were taken within ASME Section III Task Group Weld Residual to ensure mitigative actions, such as surface stress improvement (SSI), are when a construction repair made on that will be wetted susceptible SCC. The intent minimize potential for SCC in operation by mitigating potentially areas during construction. However, no...

10.1115/pvp2022-85151 article EN Volume 1: Codes and Standards 2022-07-17

Wall thinning of carbon steel pipe components due to Flow-Accelerated Corrosion (FAC) is one the most serious problems integrity steam cycle piping system in Nuclear Power Plants (NPP). If thickness a component reduced below critical level, it cannot sustain pressure and consequently results leakage or rupture. For this reason, wall by FAC has been inspected secondary side systems NPPs. The objective research verify confidence measurement conducting Round Robin Test (RRT). 12 inspectors from...

10.1299/jsmeatem.2007.6._p-09-1_ article EN The Abstracts of ATEM International Conference on Advanced Technology in Experimental Mechanics Asian Conference on Experimental Mechanics 2007-01-01

The reactor vessel closure head has many CEDM nozzles through which the control element drive mechanisms pass. nozzle weld region of is composed Alloy 600 material. It been found that cracks occur due to high stress generated during normal operation nuclear power plant and contact environment with primary cooling water. Seal Weld Repair blocks environmental factor may causes water corrosion cracking(PWSCC) by covering susceptible PWSCC 690 resistant cracking. In this study, a finite analysis...

10.5781/jwj.2018.36.2.7 article EN cc-by-nc-nd Journal of Welding and Joining 2018-04-03
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