Annealing textures in zircaloy tubing

Tenckhoff, E.; Rittenhouse, P.L.

doi:10.1016/0022-3115(70)90022-x

Cited by 37 publications

(16 citation statements)

References 4 publications

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“…The texture can be further modified by annealing: during recrystallization the basal poles do not change significantly. However, zirconium crystals rotate around their c axis by ±30°, so instead of a first order prism, a second order prism (1 1 2 0) pole becomes parallel to the AD [10]. The goal of this work was to study texture changes in Zr1Nb alloy caused by creep.…”

Section: Introductionmentioning

confidence: 97%

Effect of creep and α-Zr ↔ (α + β)-Zr transition in Zr1Nb cladding on texture analyzed by neutron diffraction

Vetvicka¹

2014

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 97%

Effect of creep and α-Zr ↔ (α + β)-Zr transition in Zr1Nb cladding on texture analyzed by neutron diffraction

Vetvicka¹

2014

Journal of Nuclear Materials

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“…Zr alloys' in-reactor behaviors (such as corrosion, mechanical strength, creep, and irradiation-induced growth) are mainly controlled by its alloying elements and thermo-mechanical processing during pilgering [2][3][4]. First generation zirconium alloys, such as Zircaloy-2 and Zircaloy-4, contain alloying elements such as Sn, Fe, and Cr.…”

Section: Introductionmentioning

confidence: 99%

Out-of-Pile Mechanical Performance and Microstructure of Recrystallized ZR-1.5 Nb-O-S Alloys

Ko¹,

Lee²,

Hong

2011

Nuclear Engineering and Technology

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“…[2][3][4] The first generation zirconium alloys such as Zircaloy-2 and Zircaloy-4 contain alloying elements such as Sn, Fe and Cr and have been used for several decades in the nuclear reactors without any significant performance problems. The efforts to enhance the safety and economy of nuclear power plants, however, have led to the development of the second generation Zr alloys such as Zirlo™ (trademark of Westinghouse Electric Co.), M5™ (trademark of AREVANP), and other Zr alloys.…”

Section: Introductionmentioning

confidence: 99%

Mechanical and Oxidation Properties of Cold-Rolled Zr-Nb-O-S Alloys

Lee¹,

Nathanael²,

Shin³

et al. 2011

Korean. J. Mater. Res.

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The stress-strain responses and oxidation properties of cold-rolled Zr-1.5Nb-O and Zr-1.5Nb-O-S alloys were studied. The U.T.S. (ultimate tensile strength) of cold-rolled Zr-1.5Nb-O-S alloy with 160 ppm sulfur (765 MPa) were greater than that of Zr-1Nb-1Sn-0.1Fe alloy (750 MPa), achieving an excellent mechanical strength even after the elimination of Sn, an effective solution strengthening element. The addition of sulfur increased the strength at the expense of ductility. However, the ductile fracture behavior was observed both in Zr-Nb-O and Zr-Nb-O-S alloys. The beneficial effect of sulphur on the strengthening was observed in the cold rolled Zr-1.5Nb-O-S alloys. The activation volume of cold-rolled Zr-1.5Nb decreased with sulfur content in the temperature region of dynamic strain aging associated with oxygen atoms. Insensitivity of the activation volume to the dislocation density and the decrease of the activation volume at a higher temperature where the dynamic strain aging occurs support the suggestion linking the activation volume with the activated bulge of dislocations limited by segregation of oxygen and sulfur atoms. The addition of sulfur was also found to improve the oxidation resistance of ZrNb-O alloys.

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Annealing textures in zircaloy tubing

Cited by 37 publications

References 4 publications

Effect of creep and α-Zr ↔ (α + β)-Zr transition in Zr1Nb cladding on texture analyzed by neutron diffraction

Effect of creep and α-Zr ↔ (α + β)-Zr transition in Zr1Nb cladding on texture analyzed by neutron diffraction

Out-of-Pile Mechanical Performance and Microstructure of Recrystallized ZR-1.5 Nb-O-S Alloys

Mechanical and Oxidation Properties of Cold-Rolled Zr-Nb-O-S Alloys

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