Hao Jiang

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

Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel

Hong Wang, Jy-An John Wang, Ting Tan et al. · Journal of Nuclear Materials · 2013 · 31 citations

Engineering, Mechanical Engineering, Nuclear Engineering +16

High burn-up spent nuclear fuel transport reliability investigation

Jy-An John Wang, Hong Wang, Hao Jiang et al. · Nuclear Engineering and Design · 2018 · 25 citations · Full text

Engineering, Nuclear Engineering, Nuclear Materials +9

Methodology for mechanical property testing of fuel cladding using an expanding plug wedge test

Hao Jiang, Jy-An John Wang · Journal of Nuclear Materials · 2013 · 24 citations

Engineering, Materials Engineering, Materials Science +12

Spent nuclear fuel system dynamic stability under normal conditions of transportation

Hao Jiang, Jy-An John Wang · Nuclear Engineering and Design · 2016 · 20 citations · Full text

Engineering, Nuclear Engineering, Systems Engineering +12