S. S. Hwang
Korea Atomic Energy Research Institute(KR)
Publications by Year
Research Areas
Hydrogen embrittlement and corrosion behaviors in metals, Corrosion Behavior and Inhibition, Nuclear Materials and Properties, Mechanical Failure Analysis and Simulation, High Temperature Alloys and Creep
Most-Cited Works
- → Electrochemical Interaction of Lead with Alloy 600 and Alloy 690 in High-Temperature Water(2002)32 cited
- → Effect of serrated grain boundary on stress corrosion cracking of Alloy 600(2018)19 cited
- → Degradation of Alloy 600 Steam Generator Tubes in Operating Pressurized Water Reactor Nuclear Power Plants(2003)17 cited
- → Elastic‐plastic fracture mechanics assessment for steam generator tubes with through‐wall cracks(2007)12 cited
- → Enhancement of leak rate estimation model for corroded cracked thin tubes(2009)9 cited
- → Effect of microstructure on stress corrosion cracking of alloy 600 and alloy 690 in 40% NaOH(2001)8 cited
- → Effects of current density and agitation on co-deposition behaviour of electrodeposited Ni–TiO2 composite coating(2015)8 cited
- → Oxidation Behavior of Steel With Cr Content and Water Flow Rate(2017)7 cited
- → Effect of Local Strain Distribution of Cold-Rolled Alloy 690 on Primary Water Stress Corrosion Crack Growth Behavior(2017)5 cited
- → Effects of Grain Boundary Morphologies on Stress Corrosion Cracking of Alloy 600(2017)3 cited