Zirconium in Nuclear Applications

American Society anisotropy anodizing ASTM axial basal poles behavior biaxial burst test cold-worked corrosion rate coupons crack creep rate creep strain curve decrease defect deformation depleted zones diameter direction dislocation ductility effect elongation fluence flux fracture fracture toughness fuel grain boundary hoop stress hydride hydrogen in-flux in-reactor increase intermetallic interstitials iodine irradiation Journal of Nuclear longitudinal loop measured mechanical properties metal metallographic Metallurgical methanol microstructure n/m² niobium Nuclear Materials observed orientation oxide oxide film oxygen parameters percent plane plane strain plastic plate pole figure pressure tubes quenched radiation reactor reduction rolling room temperature sample SGHWR shown in Fig Society for Testing solution specimens stress-strain stress-strain curve structure surface Table tangential tensile properties Testing and Materials texture tion transverse uniaxial unirradiated vacancies values void wall thickness weight gain yield strength Zircaloy Zircaloy tubing Zircaloy-2 zirconium alloys Zr-Nb