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Jong-Dae Hong
Jong-Dae Hong
Verified email at kaeri.re.kr
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Year
Low cycle fatigue behavior of alloy 690 in simulated PWR water—Effects of dynamic strain aging and hydrogen
JD Hong, J Lee, C Jang, TS Kim
Materials Science and Engineering: A 611, 37-44, 2014
342014
ENVIRONMENTAL FATIGUE OF METALLIC MATERIALS IN NUCLEAR POWER PLANTS–A REVIEW OF KOREAN TEST PROGRAMS
C Jang, H Jang, JD Hong, H Cho, TS Kim, JG Lee
Nuclear Engineering and Technology 45 (7), 929-940, 2013
272013
Effects of mixed strain rates on low cycle fatigue behaviors of austenitic stainless steels in a simulated PWR environment
JD Hong, C Jang, TS Kim
International Journal of Fatigue 82, 292-299, 2016
252016
Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment
J Chen, A Nurrochman, JD Hong, TS Kim, C Jang, Y Yi
Nuclear Engineering and Technology 51 (2), 479-489, 2019
202019
Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage
JS Kim, JD Hong, YS Yang, DH Kook
Journal of Nuclear Materials 492, 253-259, 2017
202017
Measurement of Zircaloy-4 cladding tube deformation using a three-dimensional digital image correlation system with internal transient heating and pressurization
DH Kim, GH Choi, H Kim, C Lee, SU Lee, JD Hong, HS Kim
Nuclear Engineering and Design 363, 110662, 2020
162020
Effects of heat treatment on mechanical properties and sensitization behavior of materials in dissimilar metal weld
HS Kim, J Shin, BS Kong, S Hong, S Oh, JD Hong, C Jang, S Lee
International Journal of Pressure Vessels and Piping 172, 17-27, 2019
132019
PFM application for the PWSCC Integrity of Ni-base Alloy Welds-Development and Application of PINEP-PWSCC
JD Hong, C Jang, TS Kim
Nuclear Engineering and Technology 44 (8), 961-970, 2012
112012
Delayed hydride cracking assessment of PWR spent fuel during dry storage
JD Hong, HC Kim, JS Kim, YS Yang, DH Kook
Nuclear Engineering and Design 322, 324-330, 2017
82017
Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRs
JD Hong, C Jang
Proceedings of the ASME Pressure Vessel and Piping Division/K-PVP Conference …, 2010
62010
The effects of dissolved hydrogen contents on the low cycle fatigue behaviors of a 316LN stainless steel in simulated PWR conditions
PY Cho, C Jang, H Jang, JD Hong, TS Kim, JG Lee
62010
Measurement and investigation of mechanical properties of a partial oxide dispersion strengthened Zircaloy-4 tube via an instrumented indentation test
DH Kim, JD Hong, H Kim, J Kim, HS Kim, H Guim
Materials Today Communications 27, 102210, 2021
52021
Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding
JD Hong, M Park, AMA Holston, J Stjärnsäter, D Kook
Journal of Nuclear Materials 543, 152596, 2021
52021
Low cycle fatigue behavior of hot-bent 347 stainless steel in a simulated PWR water environment
J Lee, MG Seo, JD Hong, TS Kim, C Jang
Journal of Mechanical Science and Technology 30, 4931-4936, 2016
52016
Mechanical Property Degradation of Unirradiated Zircaloy-4 Cladding After Creep Deformation
JD Hong, E Kim, YS Yang, DH Kook
Nuclear Technology 203, 282-292, 2018
42018
Environmental fatigue behaviors of Ni-base alloys in PWR primary water environments
JD Hong, TS Kim, YS Lee, C Jang
2013 ICG-EAC, 2013
42013
Enhanced crud resistance of CrAl coated ATF claddings in simulated PWR conditions
SE Kim, DH Kim, JD Hong, JY Kim, HG Kim
Journal of Nuclear Materials 578, 154357, 2023
32023
Study of the mechanical properties and effects of particles for oxide dispersion strengthened Zircaloy-4 via a 3D representative volume element model
DH Kim, JD Hong, H Kim, J Kim, HS Kim
Nuclear Engineering and Technology 54 (5), 1549-1559, 2022
32022
Qualitative approach to understand fatigue behavior of CrAl-ODS-Zr alloy ATF cladding
JD Hong, JY Kim
2021 KNS spring meeting, 2021
32021
Comparison for spent fuel behavior of PWR and SMRs
G Nam, JD Hong, Y Lee
Fuel 5, 0.64, 2020
32020
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