Zirconium in the Nuclear Industry: Sixth International Symposium Sponsored by ASTM Committee B-10 on Reactive and Refractory Metals, Vancouver, B.C., 28 June-1 July 1982, Issue 824
American Society for Testing and Materials, 1984 - Nuclear fuel claddings - 846 pages
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New Process for Zirconium and Hafnium SeparationL MOULIN
New Solvent Extraction Process for Zirconium and Hafnium
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Adamson alloys American Society anisotropy annealing ASTM ASTM STP Atomic Energy autoclave axial basal pole behavior burst calculated Chalk River circumferential cold-worked concentration conium cooling corrosion crack growth creep and growth D. G. Franklin decrease deformation dependence diameter dislocation density effect experimental fluence fuel rod furnace grain boundaries growth rate growth strains hafnium hoop stress hydride hydrogen in-reactor increase initial iodine irradiation irradiation growth Journal of Nuclear layer thickness LiOH longitudinal loops measured mechanical melt metal microstructure neutron Nuclear Industry Nuclear Materials observed orientation oxide film oxide layer oxygen parameters plane pole figure predicted pressure tubes produced radial reactor recrystallization SCCIG shown in Fig simulators Society for Testing specimens steam strain rate stress surface Table tensile Testing and Materials texture thermal tion transient transverse ture velocity versus weight gain yield strength Zircaloy Zircaloy-2 zirconium alloys zirconium tetrachloride