Young-Ho Lee

Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs

Hyung‐Il Kim, Il-Hyun Kim, Yang‐Il Jung et al. · Journal of Nuclear Materials · 2018 · 83 citations

Engineering, Materials Engineering, Materials Science +13

Influence of contact shape and supporting condition on tube fretting wear

Hyung-Kyu Kim, Young-Ho Lee · Wear · 2003 · 63 citations

Engineering, Materials Engineering, Materials Science +9

Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition

Young-Ho Lee, Hyung-Kyu Kim · Wear · 2013 · 57 citations

Engineering, Materials Engineering, Nuclear Engineering +16

A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel

Young-Ho Lee, Thak Sang Byun · Journal of Nuclear Materials · 2015 · 46 citations · Full text

Engineering, Materials Engineering, Materials Science +15

On the geometry of the fuel rod supports concerning a fretting wear failure

Hyung-Kyu Kim, Young-Ho Lee, Kanghee Lee · Nuclear Engineering and Design · 2008 · 44 citations

Natural Sciences, Materials Engineering, Materials Science +13