Je-Yong Oh

Three-dimensional simulation of threshold porosity for fission gas release in the rim region of LWR UO2 fuel

Yang-Hyun Koo, Je-Yong Oh, Byung-Ho Lee et al. · Journal of Nuclear Materials · 2003 · 15 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +16

Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO ₂ Fuels

Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh et al. · Nuclear Technology · 2007 · 15 citations

Engineering, Nuclear Engineering, Heat Transfer +16

Measurement of the specific heat of Zr–40wt%U metallic fuel

Byung‐Ho Lee, Jin-Sik Cheon, Yang-Hyun Koo et al. · Journal of Nuclear Materials · 2007 · 13 citations

Natural Sciences, Materials Engineering, Materials Science +14

Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling

Jin-Sik Cheon, Byung‐Ho Lee, Yang-Hyun Koo et al. · Nuclear Engineering and Design · 2004 · 10 citations

Engineering, Materials Science, Mechanical Engineering +17