Yoon-Suk Chang
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Previous Organizations / Institutes
The organizations / institutes from the scholar's other articles in the past ten years
Yoon-Suk Chang has a total of 115 co-authors. Here are the top co-authors by number of shared publications:
Jae Min Sim
Department of Nuclear Engineering, Kyung Hee University, Yongin-si, Korea
7 shared publicationsSeung Hyun Kim
6 shared publicationsSang Yun Je
Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104, Republic of Korea
5 shared publications- Belal Almomani
Department of Mechanical Engineering, King Fahd University of Petroleum & Minerals, Dhahran, Saudi Arabia
4 shared publications Tae-Yong Kim
4 shared publicationsChoengryul Choi
3 shared publications
Latest Publications
- Open Access
- 11 July 2026
- Published by Elsevier in SSRN Electronic Journal
Evaluation of fracture resistance of austenitic stainless steel under cryogenic and hydrogen conditions using an integrated constitutive model
The expansion of liquid hydrogen (LH₂) technologies has increased the demand for structural materials that maintain fracture resistance under combined cryogenic and hydrogen conditions. Although austenitic stainless steels (ASSs) are widely regarded as viable candidates for LH₂ tanks, multiple degradation mechanisms associated with hydrogen transport and phase transformation can induce competition between ductile failure and quasi-cleavage fracture. This study evaluates the fracture resistance of ASS 316L by formulating an integrated constitutive model developed in conjunction with mechanical tests under representative temperature and hydrogen conditions. A plasticity model was constructed by incorporating hydrogen transport and martensite evolution under different stress states. Finite element analyses of V-notched specimens were performed to calibrate the parameters of a mixed-mode damage model based on a ductile damage formulation with a critical stress criterion implemented via user-defined subroutines. Subsequently, crack growth analyses as well as tests of compact tension specimens were conducted, enabling the systematic assessment of the sensitivity of fracture resistance of ASS 316L under cryogenic and hydrogen conditions, and demonstrating the applicability and extensibility of the proposed constitutive model.
- 11 July 2026
- Published by Elsevier in SSRN Electronic Journal
Open AccessEvaluation of fracture resistance of austenitic stainless steel under cryogenic and hydrogen conditions using an integrated constitutive model
The expansion of liquid hydrogen (LH₂) technologies has increased the demand for structural materials that maintain fracture resistance under combined cryogenic and hydrogen conditions. Although austenitic stainless steels (ASSs) are widely regarded as viable candidates for LH₂ tanks, multiple degradation mechanisms associated with hydrogen transport and phase transformation can induce competition between ductile failure and quasi-cleavage fracture. This study evaluates the fracture resistance of ASS 316L by formulating an integrated constitutive model developed in conjunction with mechanical tests under representative temperature and hydrogen conditions. A plasticity model was constructed by incorporating hydrogen transport and martensite evolution under different stress states. Finite element analyses of V-notched specimens were performed to calibrate the parameters of a mixed-mode damage model based on a ductile damage formulation with a critical stress criterion implemented via user-defined subroutines. Subsequently, crack growth analyses as well as tests of compact tension specimens were conducted, enabling the systematic assessment of the sensitivity of fracture resistance of ASS 316L under cryogenic and hydrogen conditions, and demonstrating the applicability and extensibility of the proposed constitutive model.
- Open Access
- 10 December 2025
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 58 (4)
Seismic analyses of i-SMR CV supports employing a component mode synthesis technique
- 10 December 2025
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 58 (4)
Open AccessSeismic analyses of i-SMR CV supports employing a component mode synthesis technique
- 22 April 2025
- Published by Elsevier in Engineering Failure Analysis
- Vol. 176
Failure assessment of degraded baffle former bolts retrieved from a nuclear power plant
- 22 April 2025
- Published by Elsevier in Engineering Failure Analysis
- Vol. 176
Failure assessment of degraded baffle former bolts retrieved from a nuclear power plant
- 17 February 2025
- Published by Elsevier in Progress in Nuclear Energy
- Vol. 182
Analysis schemes to evaluate HELB-induced blast waves
- 17 February 2025
- Published by Elsevier in Progress in Nuclear Energy
- Vol. 182
Analysis schemes to evaluate HELB-induced blast waves
- 1 February 2025
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 433
Assessing the impact of postulated voids on PCCV structural integrity
- 1 February 2025
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 433
Assessing the impact of postulated voids on PCCV structural integrity
- 19 November 2024
- Published by Elsevier in International Journal of Pressure Vessels and Piping
- Vol. 213
Geometry effects on the pressure-temperature limit curve of small modular reactor vessel
- 19 November 2024
- Published by Elsevier in International Journal of Pressure Vessels and Piping
- Vol. 213
Geometry effects on the pressure-temperature limit curve of small modular reactor vessel