Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings

Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions

S. Leistikow, G. Schanz · Nuclear Engineering and Design · 1987 · 171 citations

Engineering, Materials Engineering, Materials Science +16

Charpy impact energy, fracture toughness and ductile–brittle transition temperature of dual-phase 590 Steel

Y.J. Chao, Jim Ward, R. G. Sands · Materials & Design (1980-2015) · 2005 · 141 citations

Engineering, Materials Engineering, Materials Science +17

Comparative studies on high-temperature corrosion of ZrNb1 and Zircaloy-4

J. Böhmert, M. Dietrich, J. Linek · Nuclear Engineering and Design · 1994 · 37 citations

Natural Sciences, Materials Engineering, Materials Science +14

Ballooning Experiments with VVER Cladding

Zoltán Hózer, Csaba Gyuőri, Márta Horváth et al. · Nuclear Technology · 2005 · 31 citations

Engineering, Materials Engineering, Materials Science +17

Cladding tube deformation and core emergency cooling in a loss of coolant accident of a pressurized water reactor

F.J. Erbacher · Nuclear Engineering and Design · 1987 · 25 citations

Engineering, Manufacturing Engineering, Heat Transfer +16