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Jae Ho Yang
Jae Ho Yang
在 kaeri.re.kr 的电子邮件经过验证
标题
引用次数
引用次数
年份
Development status of accident-tolerant fuel for light water reactors in Korea
HG Kim, JH Yang, WJ Kim, YH Koo
Nuclear Engineering and Technology 48 (1), 1-15, 2016
3222016
Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions
DJ Park, HG Kim, YI Jung, JH Park, JH Yang, YH Koo
Journal of nuclear materials 482, 75-82, 2016
1652016
KAERI’s development of LWR accident-tolerant fuel
YH Koo, JH Yang, JY Park, KS Kim, HG Kim, DJ Kim, YI Jung, KW Song
Nuclear technology 186 (2), 295-304, 2014
1262014
Fabrication of micro-cell UO2–Mo pellet with enhanced thermal conductivity
DJ Kim, YW Rhee, JH Kim, KS Kim, JS Oh, JH Yang, YH Koo, KW Song
Journal of Nuclear Materials 462, 289-295, 2015
1072015
Microwave process for sintering of uranium dioxide
JH Yang, KW Song, YW Lee, JH Kim, KW Kang, KS Kim, YH Jung
Journal of nuclear materials 325 (2-3), 210-216, 2004
552004
UO2–UN composites with enhanced uranium density and thermal conductivity
JH Yang, DJ Kim, KS Kim, YH Koo
Journal of Nuclear Materials 465, 509-515, 2015
542015
Crystal structure and B-site ordering in antiferroelectric Pb (Mg1/2W1/2) O3, Pb (Co1/2W1/2) O3 and Pb (Yb1/2Nb1/2) O3
WK Choo, HJ Kim, JH Yang, H Lim, JY Lee, JR Kwon, CH Chun
Japanese journal of applied physics 32 (9S), 4249, 1993
531993
Development status of microcell UO2 pellet for accident-tolerant fuel
DJ Kim, KS Kim, DS Kim, JS Oh, JH Kim, JH Yang, YH Koo
Nuclear Engineering and Technology 50 (2), 253-258, 2018
462018
State-of-the-art report on light water reactor accident-tolerant fuels
K Pasamehmetoglu, S Massara, D Costa, S Bragg-Sitton, M Moatti, ...
Organisation for Economic Co-Operation and Development, 2018
462018
A fabrication technique for a UO2 pellet consisting of UO2 grains and a continuous W channel on the grain boundary
JH Yang, KW Song, KS Kim, YH Jung
Journal of nuclear materials 353 (3), 202-208, 2006
462006
Microstructure and mechanical behavior of Zr substrates coated with FeCrAl and Mo by cold-spraying
DJ Park, HG Kim, YI Jung, JH Park, JH Yang, YH Koo
Journal of Nuclear Materials 504, 261-266, 2018
422018
A mechanism for the sintered density decrease of UO2–Gd2O3 pellets under an oxidizing atmosphere
KW Song, KS Kim, JH Yang, KW Kang, YH Jung
Journal of nuclear materials 288 (2-3), 92-99, 2001
422001
Effect of step wise variation of oxygen potential during the isothermal sintering on the grain growth behavior in Cr2O3 doped UO2 pellets
JH Yang, KS Kim, IH Nam, JS Oh, DJ Kim, YW Rhee, JH Kim
Journal of nuclear materials 429 (1-3), 25-33, 2012
412012
Development of surface modified Zr cladding by coating technology for ATF
HG Kim, IH Kim, YI Jung, DJ Park, JH Yang, YH Koo
Proceedings of the Top Fuel, 1157-1163, 2016
392016
Fabrication and Thermal Conductivity of (Th,U)O2 Pellets
JH Yang, KW Kang, KW Song, CB Lee, YH Jung
Nuclear Technology 147 (1), 113-119, 2004
392004
The solidus and liquidus temperatures of UO2–Gd2O3 and UO2–Er2O3 fuels
KW Kang, JH Yang, JH Kim, YW Rhee, DJ Kim, KS Kim, KW Song
Thermochimica acta 455 (1-2), 134-137, 2007
362007
Effects of MnO-Al2O3 on the Grain Growth and High-Temperature Deformation Strain of UO2 Fuel Pellets
KW Kang, JH Yang, JH Kim, YW Rhee, DJ Kim, KS Kim, KW Song
Journal of nuclear science and technology 47 (3), 304-307, 2010
312010
Strengthening of Zircaloy-4 using Y2O3 particles by a laser-beam-induced surface treatment process
YI Jung, HG Kim, IH Kim, SH Kim, JH Park, DJ Park, JH Yang, YH Koo
Materials & Design 116, 325-330, 2017
282017
Progress of surface modified Zr cladding development for ATF at KAERI
HG Kim, IH Kim, YI Jung, DJ Park, JH Park, JH Yang, YH Koo
Proceedings of the 2017 Water Reactor Fuel Performance Meeting, Ramada Plaza …, 2017
242017
Surface treatment to form a dispersed Y2O3 layer on Zircaloy-4 tubes
YI Jung, HG Kim, HU Guim, YS Lim, JH Park, DJ Park, JH Yang
Applied surface science 429, 272-277, 2018
222018
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