Showing results 1 to 11 of 11
400 degrees C aging embrittlement of FeCrAl alloys: Microstructure and fracture behavior Kim, Hyunmyung; Subramanian, Gokul Obulan; Kim, Chaewon; Jang, Hun; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.743, pp.159 - 167, 2019-01 |
A combinatorial approach for the synthesis and analysis of AlxCryMozNbTiZr high-entropy alloys: Oxidation behavior Waseem, Owais Ahmed; Auyeskan, Ulanbek; Lee, Hyuck-Mo; Ryu, Ho Jin, JOURNAL OF MATERIALS RESEARCH, v.33, no.19, pp.3226 - 3234, 2018-10 |
Corrosion resistance of weight reduced AlxCrFeMoV high entropy alloys Raza, Ahmad; Abdulahad, Syed; Kang, Byungchul; Ryu, Ho Jin; Hong, Soon Hyung, APPLIED SURFACE SCIENCE, v.485, pp.368 - 374, 2019-08 |
Estimation of plasma parameters of X-pinch with time-resolved x-ray spectroscopy Ham, Seunggi; Ryu, Jonghyeon; Lee, Hakmin; Park, Sungbin; Ghim, Young-Chul; Hwang, YS; Chung, Kyoung-Jae, MATTER AND RADIATION AT EXTREMES, v.8, no.3, 2023-05 |
Grain Boundary Sliding in Aluminum Nano-Bi-Crystals Deformed at Room Temperature Aitken, Zachary H.; Jang, Dongchan; Weinberger, Christopher R.; Greer, Julia R., SMALL, v.10, no.1, pp.100 - 108, 2014-01 |
Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth Iltis, X.; Zacharie-Aubrun, I.; Ryu, Ho Jin; Park, J. M.; Leenaers, A.; Yacout, A. M.; Keiser, D. D.; et al, JOURNAL OF NUCLEAR MATERIALS, v.495, pp.249 - 266, 2017-11 |
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500-1500 degrees C in steam Kim, Chaewon; Tang, Chongchong; Grosse, Mirco; Maeng, Yunhwan; Jang, Changheui; Steinbrueck, Martin, JOURNAL OF NUCLEAR MATERIALS, v.564, 2022-06 |
Performance evaluation of U-Mo/Al dispersion fuel by considering a fuel-matrix interaction Ryu, Ho Jin; Kim, Yeon Soo; Park, Jong Man; Chae, Hee Taek; Kim, Chang Kyu, NUCLEAR ENGINEERING AND TECHNOLOGY, v.40, no.5, pp.409 - 418, 2008-08 |
Phase analyses of silicide or nitride coated U-Mo and U-Mo-Ti particle dispersion fuel after out-of-pile annealing Kim, Woo Jeong; Palancher, Herve; Ryu, Ho Jin; Park, Jong Man; Nam, Ji Min; Bonnin, Anne; Honkimaeki, Veijo; et al, JOURNAL OF ALLOYS AND COMPOUNDS, v.589, pp.94 - 100, 2014-03 |
Surface modification effects of SiC tile on the wettability and interfacial bond strength of SiC tile/Al7075-SiCp hybrid composites Park, Jongbok; Lee, Junho; Jo, I; Cho, S; Lee, SK; Lee, SB; Ryu, Ho Jin; et al, SURFACE COATINGS TECHNOLOGY, v.307, pp.399 - 406, 2016-12 |
The modeling and simulation of the thermal conductivity of irradiated U-Mo dispersion fuel: Estimation of the thermal conductivity of the interaction layer Mistarihi, Qusai M.; Hwang, Jun Teak; Ryu, Ho Jin, JOURNAL OF NUCLEAR MATERIALS, v.510, pp.199 - 209, 2018-11 |
Discover