Comparison of Mechanical Properties of Zr-1%Nb and Zr-2.5%Nb Alloys

Vázquez, Carolina; Fortis, A.M.; Bozzano, Patricia B.

doi:10.1016/j.mspro.2015.04.099

Cited by 9 publications

(4 citation statements)

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“…As a result, a significant loss of strength and ductility was observed. The same behavior was identified by Vazquez et al 13 when studying the effect of hydrogen on Zr-1Nb and Zr-2.5Nb alloys. The size of the secondary cracks increased in relation to the non-hydrogenated condition, 500 µm for the Zr-0.9Nb-0.1Mn alloy and 20 µm for the Zr-0.6Nb-0.4Mn alloy.…”

Section: Resultssupporting

confidence: 81%

“…TEM micrographs for the Zr-0.6Nb-0.4Mn alloy after heat treatment at 923 K for 2 h, Figure 4, show the presence of spherical and well-dispersed precipitates, with a mean radius of 1.8 nm in the zirconium matrix, confirming TC-Prisma simulation results, presented in Table 1. The development of microstructures containing nanoparticles β-Nb, can enhance critical properties as corrosion and creep resistance, as well as influence the post-irradiation mechanical behavior of the material 1,13 .…”

Section: Resultsmentioning

confidence: 99%

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Hydrogen Effect on Zr-Nb-Mn Alloys for Nuclear Reactor Application

2019

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Zr-Nb-Mn alloys were developed to investigate hydrogen diffusion and its effects among different manganese additions. Thermo-Calc ® and TC-Prisma simulations were used to determine the studied chemical compositions and to estimate the volume fraction and the mean radius of precipitates. Three compositions were chosen to be melted and thermomechanically processed, resulting in an α-Zr matrix with fine β-Nb precipitation. TDS results indicated that hydrogen diffusion coefficient was 10 -12 m 2 .s -1 for all the analyzed compositions. The manganese addition increased the strength while ductility was maintained. Although optical microscopy revealed that the increase of manganese content resulted in less oriented hydrides, the reduction in ductility was similar for the three studied compositions. Results showed manganese as a promising addition element for zirconium alloys due to the increase of hydrogen solubility, the good relationship between strength and ductility and the morphology of the hydrides.

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Section: Resultssupporting

confidence: 81%

Section: Resultsmentioning

confidence: 99%

Hydrogen Effect on Zr-Nb-Mn Alloys for Nuclear Reactor Application

2019

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“…Data of constant Tafel, corrosion potential and corrosion rate with different immersion time. Niobium is one of betha stabilizers or beta stabilizer element for zirconium alloys, β phase has better corrosion resistance compared to α phase, in this study the addition of Niobium element in Zr-10Mo binary alloy is conducted as it can stabilize and increase β phase, so the addition of Niobium element by 1%, 3% and 5% can increase corrosion resistance, Niobium element is also more reactive to form a passive layer compared to Molybdenum element (18).…”

Section: Resultsmentioning

confidence: 99%

CORROSION BEHAVIOR OF Zr-10Mo ALLOYS IN NIOBIUM-DOPED LACTATE RINGER’S SOLUTION

Prastika

Ambardi

Prajitno

2019

jsmi

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CORROSION BEHAVIOR OF Zr-10Mo ALLOYS IN NIOBIUM-DOPED LACTATE RINGER'S SOLUTION. This research discusses the corrosion behavior of Zr-10Mo alloys in Niobium-doped lactate ringer's solution. The addition of Niobium of 1%, 3% and 5% on Zr-10Mo alloys aims to study the effect of adding Niobium to the hardness, microstructure and corrosion resistance of Zr-Mo alloys. The alloys are made by melting the materials of Zr, Mo and Nb with a certain percentage of weight using single arc melting furnace in Argon atmosphere with high purity and Tungsten eletrodes. The alloys (as cast) are subjected to hardness testing using C-scale rockwell, microstructure using optical microscopy, compounds and phases in the alloys (as cast) using XRD and corrosion testing using polarization method in lactate ringers' solution. The hardness value increases by the addition of Niobium, Zr-10Mo-1Nb alloy of 34 HRC, Zr-10Mo-3Nb alloy of 38 HRC and Zr-10Mo-5Nb alloy of 41.5 HRC. The basketweave-shaped microstructure with the addition of Niobium creates relatively smaller grain size. The value of corrosion rate decrases by the addition of Niobium at the immersion times of 0 minute, 60 minutes and 120 minutes, Zr-10Mo-1Nb alloy of 4.208 mpy, Zr-10Mo-3Nb alloy of 3.538 mpy and Zr-10Mo-5Nb alloy of 2.813 mpy, included in the excellent category (1-5 mpy).

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“…[4][5][6][7][8], it is very important to determine the degree of embrittlement of irradiated components. In addition, it is necessary to establish how radiation affects the phases present in the precipitated material during and after irradiation [9].…”

Section: Introductionmentioning

confidence: 99%

Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation

Vázquez¹,

Zelaya²,

Fortis³

et al. 2021

J. Mater. Appl.

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Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors. During life-time of a reactor the microstructure of this alloy is affected due to, among other factors, radiation damage and hydrogen damage. In this work mechanical properties changes on neutron irradiated Zr-1wt.% Nb at low temperatures (< 100 °C) and low dose (3.5 ´ 1023 n m-2 (E > 1 MeV)) were correlated with hydrides and crystal defects evolution during irradiation. To achieve this propose, tensile tests of: 1) Non-hydrided and non-irradiated material, 2) Hydrided and non-irradiated material and 3) Hydrided and irradiated material were performed at 25 ºC and 300 ºC. Different phases, hydrides and second phase precipitates were characterized by transmission electron microscopy (TEM) techniques. For the hydrided and irradiated material, the ductility decreased sharply with respect to the hydrided and non-irradiated material, among other factors, due to the change in the microstructure produced mainly by neutron irradiation. Even if the presence of the hydride ζ (zeta) was observed, both in the irradiated and non-irradiated material, tensile tests showed that ζ-hydrides did not affect ductility, since hydrided samples are more ductile than non-hydrided samples.

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Comparison of Mechanical Properties of Zr-1%Nb and Zr-2.5%Nb Alloys

Cited by 9 publications

References 4 publications

Hydrogen Effect on Zr-Nb-Mn Alloys for Nuclear Reactor Application

Hydrogen Effect on Zr-Nb-Mn Alloys for Nuclear Reactor Application

CORROSION BEHAVIOR OF Zr-10Mo ALLOYS IN NIOBIUM-DOPED LACTATE RINGER’S SOLUTION

Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation

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