Recrystallization behavior of cold-rolled Zr–1Nb alloy

Tian, Hao; Wang, Xitao; Gong, Weijia; Zhou, Jun; Zhang, Hailong

doi:10.1016/j.jnucmat.2014.09.084

Cited by 20 publications

(15 citation statements)

References 23 publications

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“…The results show a decrease in hardness for annealed conditions for both compositions, indicating a full recrystallization of the microstructure, as reported in literature 8,14 . According to literature 15 , the heat treatment allowed concomitant process of aging, where precipitates are formed and grow, and recrystallization as was observed in other Zr-based alloys.…”

Section: Condition Vickers Microhardness (Hv)supporting

confidence: 87%

“…al. 8 on the recrystallization behavior of a Zr-1Nb alloy subjected to different deformations at several annealing temperatures, where full recrystallization was achieved at 600ºC after 15 minutes for a 50% deformed and 84 minutes for 30% deformed Zr-1Nb alloy, resulting in a hcp Zr matrix (grain size about 4 µm) with small β-Nb precipitates. Recrystallization levels of the cold rolled and annealed samples were evaluated by micro hardness measurements, which are presented in Table 1.…”

Section: Resultsmentioning

confidence: 99%

“…Considering that they gone through the same thermomechanical process that lead to the same degree of softening, and the proposed heat treatment was capable to induce recrystallization 8 , it is possible to predict that the final microstructure has an α-Zr matrix with recrystallized grains with β-Nb precipitates. Based on this, the slightly higher value of hydrogen absorption in Zr-1Nb-1Sn-0.1Fe could be associated with the alloying additions, specially Sn, that stabilizes α-Zr and promotes an increase of terminal solid solubility (TSS), by increasing the entropy of mixing 16 .…”

Section: Condition Vickers Microhardness (Hv)mentioning

confidence: 99%

“…Several different processing routes to optimize the microstructure of fuel rods are proposed in literature [4][5][6] with most of them indicating the recrystallized microstructure as more suitable for nuclear applications 7,8 . In fact, most of zirconium alloys in Pressurized Water Reactors (PWR) display a partial or fully-recrystallized microstructure 8 . Additionally, hydrogen interaction with zirconium alloys has long been investigated, as hydride embrittlement is the secondary life-limiting factors for fuel rods.…”

Section: Introductionmentioning

confidence: 99%

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Hydrogen Kinetics and Hydride Formation Effect on Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys for Nuclear Application

et al. 2018

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The purpose of this study was to investigate the kinetics of hydrogen absorption and hydride formation and their effect on the mechanical properties in Zr-1Nb and Zr-1Nb-1Sn-0.1Fe alloys, which were thermomechanically processed and gaseously hydrided at 320ºC under 10 bar hydrogen pressure. X-ray diffraction (XRD) confirmed the formation of α-Zr matrix after final heat treatment. The alloys absorbed almost the same amount of hydrogen, although with different kinetics. Absorption began almost immediately in Zr-1Nb alloy whilst in Zr-1Nb-1Sn-0.1Fe hydrogen absorption started after 11 h besides a faster hydrogen kinetics. Results showed that tensile strengths for both alloys were nearly independent of absorbed hydrogen. Fractographic examinations indicated ductile fractures for unhydrided condition whereas quasi-cleavage features were observed for all hydrided specimens.

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Section: Condition Vickers Microhardness (Hv)supporting

confidence: 87%

Section: Resultsmentioning

confidence: 99%

Section: Condition Vickers Microhardness (Hv)mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Hydrogen Kinetics and Hydride Formation Effect on Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys for Nuclear Application

et al. 2018

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“…Zirconium alloys are widely used for the manufacture of nuclear components as fuel claddings, guide tubes and grid spacer materials due to their high mechanical properties, low neutron absorption capacity and good corrosion resistance when submitted to harsh environments with hydrogen 1 . To guarantee these singular properties in a Pressured Water Reactor (PWR) which operates under 160 atm at 593 K, the chemical composition and the thermomechanical process must be controlled to obtain a partially or fully recrystallized microstructure to optimize critical properties 2 .…”

Section: Introductionmentioning

confidence: 99%

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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A study on annealing‐induced softening in cold drawn Cu−Cr−Sn alloy

Luo

Xie

et al. 2018

Materialwissenschaft Werkst

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The softening behavior of a 60 % cold‐drawn Cu‐0.48Cr‐0.16Sn alloy during annealing at temperatures between 450 °C and 750 °C was investigated. The mechanical properties and microstructures evolution of the alloy in both as‐drawn and annealed conditions were analyzed using hardness measurement, transmission electron microscopy (TEM) and electron back‐scatter diffraction (EBSD) technique. The results showed that the softening behavior of the alloy was strongly affected by precipitate coarsening, recovery and recrystallization, and was predominant by recrystallization when the temperature higher than 500 °C. The recrystallization kinetics was characterized by measurements of hardness. The obtained experimental data were evaluated in terms of the Johnson‐Mehl‐Avrami‐Kolmogorov model. The values of the Avrami exponent were ranged from 0.87 to 1.36, and the activation energy of recrystallization was about 117.9 kJ mol‐1 for 60 % cold‐drawn Cu−0.48Cr−0.16Sn alloy, which suggested that recrystallization process of the Cu−Cr−Sn alloy was mainly controlled by grain boundary migration. The softening resistance of the Cu−Cr−Sn alloy is stronger than that of the pure copper due to the addition of Chromium (Cr) and Tin (Sn). In addition, the reduction in strain had a positive effect on the improvement of softening resistance.

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Recrystallization behavior of cold-rolled Zr–1Nb alloy

Cited by 20 publications

References 23 publications

Hydrogen Kinetics and Hydride Formation Effect on Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys for Nuclear Application

Hydrogen Kinetics and Hydride Formation Effect on Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys for Nuclear Application

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

A study on annealing‐induced softening in cold drawn Cu−Cr−Sn alloy

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