Roger Lu

Grid-to-rod flow-induced impact study for PWR fuel in reactor

Hao Jiang, Jun Qu, Roger Lu et al. · Progress in Nuclear Energy · 2016 · 60 citations · Full text

Engineering, Nuclear Engineering, Computational Fluid Dynamics +13

Investigating grid-to-rod fretting wear of nuclear fuel claddings using a unique autoclave fretting rig

Sladjan Lazarevic, Roger Lu, Cyrille Favede et al. · Wear · 2018 · 60 citations · Full text

Engineering, Materials Engineering, Nuclear Engineering +14

Large-eddy simulation, fuel rod vibration and grid-to-rod fretting in pressurized water reactors

M Christon, Roger Lu, József Bakosi et al. · Journal of Computational Physics · 2016 · 57 citations · Full text

Engineering, Computational Engineering, Mechanical Engineering +13

Assessment of wear coefficients of nuclear zirconium claddings without and with pre-oxidation

Jun Qu, Kevin M. Cooley, Austin Shaw et al. · Wear · 2016 · 47 citations · Full text

Engineering, Materials Engineering, Materials Science +14

CASL virtual reactor predictive simulation: Grid-to-Rod Fretting wear

Roger Lu, Zeses Karoutas, T.-L. Sham · JOM · 2011 · 33 citations

Engineering, Computational Engineering, Nuclear Engineering +10