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pyungyeon cho
pyungyeon cho
Lab Engineer & Researcher, Khalifa University of Science and Technology
Verified email at ku.ac.ae
Title
Cited by
Cited by
Year
Potentiodynamic polarization behaviour of AISI type 316 stainless steel in NaCl solution
Y Yi, P Cho, A Al Zaabi, Y Addad, C Jang
Corrosion Science 74, 92-97, 2013
1152013
Effects of microstructure and residual stress on fatigue crack growth of stainless steel narrow gap welds
C Jang, PY Cho, M Kim, SJ Oh, JS Yang
Materials & Design 31 (4), 1862-1870, 2010
1142010
Passivity breakdown of 316L stainless steel during potentiodynamic polarization in NaCl solution
S Al Saadi, Y Yi, P Cho, C Jang, P Beeley
Corrosion Science 111, 720-727, 2016
1082016
Critical conditions for pit initiation and growth of austenitic stainless steels
M Al Ameri, Y Yi, P Cho, S Al Saadi, C Jang, P Beeley
Corrosion Science 92, 209-216, 2015
332015
Effect of precipitate coherency on the corrosion-induced hydrogen trapping in 2024 aluminum alloy
H Kamoutsi, GN Haidemenopoulos, H Mavros, C Karantonidis, P Floratos, ...
International Journal of Hydrogen Energy 46 (69), 34487-34497, 2021
122021
Aging phenomena during in-service creep exposure of heat-resistant steels
GN Haidemenopoulos, K Polychronopoulou, AD Zervaki, H Kamoutsi, ...
Metals 9 (7), 800, 2019
112019
Electrochemical behavior of reinforcing steel for nuclear reactor containment buildings
M Qasem, Y Yi, SA Hanaei, P Cho
IOSR Journal of Mechanical and Civil Engineering 13, 80-90, 2016
72016
Environmental Fatigue Behaviors of CF8M Stainless Steel in 310℃ Deoxygenated Water-Effects of Hydrogen and Microstructure
H Jang, P Cho, C Jang, TS Kim
Transactions of the Korean Society of Mechanical Engineers A 38 (1), 11-16, 2014
32014
Effect of Temperature Gradient on Chloride Ion Diffusion in Nuclear Reactor Containment Building Concrete
B An, P Cho, RA Shittu, TY Kim, P Rostron, A AlFantazi, Y Yi
Energies 15 (15), 5581, 2022
22022
The effects of dissolved hydrogen contents on the low cycle fatigue behaviors of a 316LN stainless steel in simulated PWR condition
C Jang, PY Cho, JD Hong, H Jang, TS Kim, JG Lee
Nuclear Plant Chemistry Conference 2010, 2010
22010
Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel
R Al Hammadi, Y Yi, W Zaki, P Cho, C Jang
Nuclear Engineering and Design 301, 24-31, 2016
12016
Low cycle fatigue of Alloy 690 and welds in a simulated PWR primary water environment
JD Hong, P Cho, TS Kim, YS Lee, C Jang
2013 Korean Nuclear Society Spring Meeting, 30-31, 2013
12013
Effect of Temperature Gradient on Chloride Ion Diffusion in Nuclear Reactor Containment Building Concrete. Energies 2022, 15, 5581
B An, P Cho, RA Shittu, TY Kim, P Rostron, A AlFantazi, Y Yi
s Note: MDPI stays neutral with regard to jurisdictional claims in published …, 2022
2022
Deliquescence of NaCl and Atmospheric Corrosion of 316L Stainless Steel
A Al Mehrzi, YS Yi, PY Cho, S Al Saadi, JS Lee, DS Choi
Advanced Materials Research 1142, 8-13, 2017
2017
Depassivation of reinforcing steel in concrete structures
S Al Saadi, P Cho, Y Yi
European Corrosion Congress, EUROCORR 2016, 2016
2016
Threshold conditions for concrete reinforcing steel corrosion in Barakah nuclear power plants, UAE
M Qasem, Y Yi, P Cho, S Al Hanaei
European Corrosion Congress, EUROCORR 2015, 915-924, 2015
2015
Semiconducting properties of surface oxides formed on austenitic stainless steel
SA Saadi, Y Yi, P Cho, C Jang, P Beeley
European Corrosion Congress, EUROCORR 2015, 575-584, 2015
2015
Effect of strain hardened microstructures on the electrochemical behaviour of 316L stainless steel
A Al Zaabi, Y Yi, P Cho, C Jang
European Corrosion Congress, EUROCORR 2013, 2013
2013
Role of Mechanical Factors in PWSCC of Stainless Steel
P Cho, Y Yi, W Zaki, C Jang
EUROCORR 2013, 2013
2013
Pitting resistance of candidate materials for nuclear-desalination plants
A Al Zaabi, Y Yi, C Jang, P Cho
Annual Conference of the Australasian Corrosion Association 2012, 687-695, 2012
2012
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