Helium bubble evolution in a Zr–Sn–Nb–Fe–Cr alloy during post-annealing: An in-situ investigation

Shen, Huahai; Peng, Shuming; Chen, B.; Naab, F.; Sun, Guangai; Zhou, Wei; Xi, Xiang; Sun, Kai; Zu, Xiaotao

doi:10.1016/j.matchar.2015.07.025

Cited by 15 publications

(5 citation statements)

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“…The size of zirconium crystal is above one micron. The insert image located at the top left in Figure 2 a is a selected area electron diffraction (SAED) pattern of the zirconium matrix along the [ 1 , 2 , 3 , 4 , 5 , 6 , 7 , 8 , 9 , 10 ] crystal orientation. According to equilibrium phase diagram of Zr-Nb alloy, the thermally stable status of a binary zirconium alloy with a few percent of Nb is the solid solution of Nb in the α-Zr matrix when the temperature is below the monotectoid reaction temperature [ 31 ].…”

Section: Resultsmentioning

confidence: 99%

“…In the past several decades, the irradiation behaviors of zirconium alloys have been widely investigated [ 5 , 6 , 7 , 8 , 9 , 10 , 11 , 12 , 13 ]. The main investigations conducted so far including the following: (i) phase changes, nanocrystallization, and amorphization [ 5 , 6 ]; (ii) particle dissolution or precipitation [ 7 ]; (iii) the effect of chemical composition and preparation technology on the irradiation behaviors [ 8 , 9 ]; (iv) helium behaviors in zirconium alloys [ 10 ]; (v) dislocation formation and characteristic [ 11 ]; (vi) post-irradiation corrosion behaviors [ 12 ]; (vii) computer simulation such as molecular dynamics for irradiation behaviors [ 13 ]. In addition, the microhardness obtained by nanoindenter is an important method for characterizing the mechanical properties before and after ion irradiation because of the limited irradiation depth.…”

Section: Introductionmentioning

confidence: 99%

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In Situ TEM Study of Microstructure Evolution of Zr-Nb-Fe Alloy Irradiated by 800 keV Kr2+ Ions

et al. 2017

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The microstructure evolution of Zr-1.1Nb-1.51Fe-0.26Cu-0.72Ni zirconium alloy, irradiated by 800 keV Kr2+ ions at 585 K using the IVEM-Tandem Facility at Argonne National Laboratory, was observed by in situ transmission electron microscopy. A number of β-Nb precipitates with a body-centered cubic (BCC) structure were distributed in the as-received zirconium alloy with micrometer-size grains. Kr2+ ion irradiation induced the growth of β-Nb precipitates, which could be attributed to the segregation of the dissolved niobium atoms in the zirconium lattice and the migration to the existing precipitates. The size of precipitates was increased with increasing Kr2+ ion fluence. During Kr2+ iron irradiation, the zirconium crystals without Nb precipitates tended to transform to the nanocrystals, which was not observed in the zirconium crystals with Nb nanoparticles. The existing Nb nanoparticles were the key factor that constrained the nanocrystallization of zirconium crystals. The thickness of the formed Zr-nanocrystal layer was about 300 nm, which was consistent with the depth of Kr2+ iron irradiation. The mechanism of the precipitate growth and the formation of zirconium nanocrystal was analyzed and discussed.

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Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

In Situ TEM Study of Microstructure Evolution of Zr-Nb-Fe Alloy Irradiated by 800 keV Kr2+ Ions

et al. 2017

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“…In addition, ( n , α) reactions produce abundant helium (He) atoms in materials. As He has extremely low solubility in metals, it tends to accumulate and precipitate into nanoscale He bubbles in nuclear structure materials [8,9,10,11,12,13,14]. Figure 1 shows typical examples of transmission electron microscope (TEM) images of He bubbles formed in Al [10], tungsten [11] and Zr [12,13,14] after He + ion irradiation.…”

Section: Introductionmentioning

confidence: 99%

“…It has been well demonstrated that even extremely low overall He concentration can lead to He embrittlement via formation of He bubbles along grain boundaries (GBs) [18,19]. In view of this, several decades of investigations have been conducted to unveil He behaviors and underlying mechanisms for He-induced degradation in metals [8,9,10,11,12,13,14,15,16,17,18,19,20,21,22,23,24]. Both experiments and atomic simulations are adopted to investigate He bubble formation, dynamic evolution and their effects on mechanical properties of metals.…”

Section: Introductionmentioning

confidence: 99%

Radiation-Induced Helium Bubbles in Metals

Han

2019

Materials

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Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors after high dose energetic particle irradiation. In the past decades, extensive studies have been conducted to explore the dynamic evolution of He bubbles under various conditions and to investigate He-induced hardening and embrittlement. In this review, we summarize the current understanding of the behavior of He bubbles in metals; overview the mechanisms of He bubble nucleation, growth, and coarsening; introduce the latest methods of He control by using interfaces in nanocrystalline metals and metallic multilayers; analyze the effects of He bubbles on strength and ductility of metals; and point out some remaining questions related to He bubbles that are crucial for design of advanced radiation-tolerant materials.

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“…Zee et al [29] reported the occurrence of blisters on the surface of Zr-2.5Nb (wt.%) alloy during 50 keV He implantation at temperatures from 100 to 773 K. They concluded that when the alloy is cold worked prior to irradiation, βNb precipitates could act as trapping sites resulting in the development of He bubbles at a fluence of 5 × 10 17 ions • cm −2 . Another in situ TEM annealing study was performed by Shen et al [30] with the alloy Zr-Sn-Nb-Fe-Cr. They irradiated with 400 keV He ions and observed that the mean size of the He bubbles increased with irradiation temperature from 300 to 1173 K and with He fluence from 0.5 × 10 17 to 5 × 10 17 ions • cm −2 .…”

Section: Introductionmentioning

confidence: 99%

Effect of He implantation on the microstructure of zircaloy-4 studied using in situ TEM

Tunes

Harrison

Greaves

et al. 2017

Journal of Nuclear Materials

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Zirconium alloys are of great importance to the nuclear industry as they have been widely used as cladding materials in light-water reactors since the 1960s. This work examines the behaviour of these alloys under He ion implantation for the purposes of developing understanding of the fundamental processes behind their response to irradiation. Characterization of zircaloy-4 samples using TEM with in situ 6 keV He irradiation up to a fluence of 2.7 × 10 17 ions • cm −2 in the temperature range of 298 to 1148 K has been performed. Ordered arrays of He bubbles were observed at 473 and 1148 K at a fluence of 1.7 × 10 17 ions • cm −2 in αZr, the hexagonal compact (HCP) and in βZr, the body centred cubic (BCC) phases, respectively. In addition, the dissolution behaviour of cubic Zr hydrides under He irradiation has been investigated.

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Helium bubble evolution in a Zr–Sn–Nb–Fe–Cr alloy during post-annealing: An in-situ investigation

Cited by 15 publications

References 50 publications

In Situ TEM Study of Microstructure Evolution of Zr-Nb-Fe Alloy Irradiated by 800 keV Kr2+ Ions

In Situ TEM Study of Microstructure Evolution of Zr-Nb-Fe Alloy Irradiated by 800 keV Kr2+ Ions

Radiation-Induced Helium Bubbles in Metals

Effect of He implantation on the microstructure of zircaloy-4 studied using in situ TEM

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