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 | 322 | 2016 |
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 | 165 | 2016 |
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 | 126 | 2014 |
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 | 107 | 2015 |
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 | 55 | 2004 |
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 | 54 | 2015 |
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 | 53 | 1993 |
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 | 46 | 2018 |
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 | 46 | 2018 |
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 | 46 | 2006 |
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 | 42 | 2018 |
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 | 42 | 2001 |
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 | 41 | 2012 |
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 | 39 | 2016 |
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 | 39 | 2004 |
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 | 36 | 2007 |
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 | 31 | 2010 |
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 | 28 | 2017 |
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 | 24 | 2017 |
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 | 22 | 2018 |