Y.W. Lee

Oxidation behavior of unirradiated UO2 pellets

Ki-Kwang Bae, B.G. Kim, Y.W. Lee et al. · Journal of Nuclear Materials · 1994 · 43 citations

Materials Science, Nuclear Ceramic, Engineering +3

Characterization of HWR fuel pellets fabricated using UO2 powders from different conversion processes

Y.W. Lee, Ming-Xing Yang · Journal of Nuclear Materials · 1991 · 22 citations

Materials Science, Chemical Engineering, Engineering +8

Study on the mechanical properties and thermal conductivity of silicon carbide-, zirconia- and magnesia aluminate-based simulated inert matrix nuclear fuel materials after cyclic thermal shock

Y.W. Lee, S.C. Lee, H.S. Kim et al. · Journal of Nuclear Materials · 2003 · 20 citations

Materials Science, Materials Engineering, Nuclear Ceramic +11

Formation mechanism of C/SiC/C multi-layers during self-propagating high-temperature synthesis

B.G. Kim, Y.W. Lee, J.W. Lee et al. · Surface and Coatings Technology · 2002 · 11 citations

Materials Science, Engineering, Applied Physics +4