Browse "NE-Journal Papers(저널논문)" by Subject AL
Showing results 6 to 11 of 11
| 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 |
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Open Access
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