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A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under
Oxidation and Deuterium Uptake of Zr2 5Nb Pressure Tubes in CANDUPHW
Evaluation of Zircaloy2 Pressure Tubes from NPDChristopher e coleman
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a-Zr accelerated alpha American Society analysis annealing annealing parameter ASTM atom probe Atomic autoclave autoclave tests axial beta blister c-component calculated chromium cold-worked composition coolant corrosion behavior corrosion rate corrosion resistance corrosion test crack tip creep curves decrease deformation deuterium diameter diffusion dislocation distribution effect electron experimental fluence fracture toughness fuel rods grain heat treatment hydride hydrogen in-reactor increase intermetallic intermetallic particles International Symposium iodine iron and chromium irradiation Journal of Nuclear liner lithium lithium hydroxide loops matrix measured mechanism microstructure N reactor neutron nickel niobium nodular corrosion nodules Nuclear Industry Nuclear Materials observed Ontario Hydro oxide oxide film oxide thickness oxygen phase Philadelphia profiles quenching ratio recrystallized shown in Fig shows Society for Testing solution specimens steam strain rate stress structure Table tensile Testing and Materials thermal tube material values weight gains Zircaloy Zircaloy-2 zirconium alloys