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Jin Weon Kim

Observed names: JIN WEON KIM, Jin-Weon Kim
Observed institutions: Oak Ridge National Laboratory, Chosun University, Korea Advanced Institute of Science and Technology, Korea University, Sunchon National University, Sejong University
ORCID: 0000-0002-2873-5960
Observed ORCID: 0000-0002-2873-5960
OpenAlex ID: A5080748690
Determination of true stress-strain curve of type 304 and 316 stainless steels using a typical tensile test and finite element analysis
2020 · Hyeong Do Kweon, Jin Weon Kim, et al. · Nuclear Engineering and Technology · 111
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Local mechanical properties of Alloy 82/182 dissimilar weld joint between SA508 Gr.1a and F316 SS at RT and 320°C
2008 · Jin Weon Kim, Kyoungsoo Lee, et al. · Journal of Nuclear Materials · 111
Residual stress prediction of dissimilar metals welding at NPPs using support vector regression
2008 · Man Gyun Na, Jin Weon Kim, et al. · Nuclear Engineering and Design · 49
Evaluation of Fracture Stress for the SiC Layer of TRISO‐Coated Fuel Particles Using a Modified Crush Test Method
2009 · Thak Sang Byun, John D. Hunn, et al. · International Journal of Applied Ceramic Technology · 35
Effect of length of thinning area on the failure behavior of carbon steel pipe containing a defect of wall thinning
2003 · Jin Weon Kim, Chi Yong Park · Nuclear Engineering and Design · 35
Numerical ductile fracture prediction of circumferential through-wall cracked pipes under very low cycle fatigue loading condition
2018 · Hyun-Suk Nam, Jong-Min Lee, et al. · Engineering Fracture Mechanics · 32
Experimental evaluation of the effect of local wall thinning on the failure pressure of elbows
2009 · Jin Weon Kim, Sung Ho Lee, et al. · Nuclear Engineering and Design · 29
A methodology for determining the true stress-strain curve of SA-508 low alloy steel from a tensile test with finite element analysis
2018 · Hyeong Do Kweon, Eun Ju Heo, et al. · Journal of Mechanical Science and Technology · 27
Analysis of tensile deformation and failure in austenitic stainless steels: Part I – Temperature dependence
2009 · Jin Weon Kim, Thak Sang Byun · Journal of Nuclear Materials · 26
Simulation of ductile fracture toughness test under monotonic and reverse cyclic loading
2017 · Hyun-Suk Nam, Jong-Min Lee, et al. · International Journal of Mechanical Sciences · 24
Effect of Loading Rate on the Fracture Behavior of Nuclear Piping Materials Under Cyclic Loading Conditions
2016 · Jin Weon Kim, Myung Rak Choi, et al. · Nuclear Engineering and Technology · 24
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Analysis of tensile deformation and failure in austenitic stainless steels: Part II – Irradiation dose dependence
2009 · Jin Weon Kim, Thak Sang Byun · Journal of Nuclear Materials · 24
Numerical prediction of thermal aging and cyclic loading effects on fracture toughness of cast stainless steel CF8A: Experimental and numerical study
2019 · Gyo-Geun Youn, Hyun-Suk Nam, et al. · International Journal of Mechanical Sciences · 22
Investigation of dynamic strain aging in SA106 Gr.C piping steel
1997 · Jin Weon Kim, In Sup Kim · Nuclear Engineering and Design · 22
Uncertainty Analysis of Data-based Models for Estimating Collapse Moments of Wall-thinned Pipe Bends and Elbows
2012 · Dong-Su Kim, Ju-Hyun Kim, et al. · Nuclear Engineering and Technology · 20
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Extracting ductile fracture toughness from small punch test data using numerical modeling
2016 · Jun-Young Jeon, Yun-Jae Kim, et al. · International Journal of Pressure Vessels and Piping · 19
The effect of load-controlled bending load on the failure pressure of wall-thinned pipe elbows
2013 · Jin Weon Kim, Min Soo Yoon, et al. · Nuclear Engineering and Design · 18
On-power Detection of Pipe Wall-thinned Defects Using Ir Thermography in Npps
2014 · JU HYUN KIM, KWAE HWAN YOO, et al. · Nuclear Engineering and Technology · 17
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Predicting ductile fracture of cracked pipes using small punch test data
2021 · Jong-Min Lee, Jin-Ha Hwang, et al. · European Journal of Mechanics - A/Solids · 16
Numerical Ductile Tearing Simulation of Circumferential Cracked Pipe Tests under Dynamic Loading Conditions
2016 · Hyun-Suk Nam, Ji-Soo Kim, et al. · Nuclear Engineering and Technology · 15
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Fuzzy Support Vector Regression Model for the Calculation of the Collapse Moment for Wall-thinned Pipes
2008 · Heon-Young Yang, Man-Gyun Na, et al. · Nuclear Engineering and Technology · 14
Estimation of collapse moment for the wall-thinned pipe bends using fuzzy model identification
2006 · Man Gyun Na, Jin Weon Kim, et al. · Nuclear Engineering and Design · 14
Crack tip fields at crack initiation and growth under monotonic and large amplitude cyclic loading: Experimental and FE analyses
2020 · Jin-Ha Hwang, Hune-Tae Kim, et al. · International Journal of Fatigue · 13
Comparison of numerical predictions with experimental burst pressures of tubes with multiple surface cracks
2018 · Myeong-Woo Lee, Ji-Seok Kim, et al. · Engineering Fracture Mechanics · 12
Prediction of residual stress in the welding zone of dissimilar metals using data-based models and uncertainty analysis
2010 · Dong Hyuk Lim, In Ho Bae, et al. · Nuclear Engineering and Design · 12
Works count: 108
Citation count: 960
H-index: 17
I10-index: 30
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