On the irradiation tolerance of nano-grained Ni–Mo–Cr alloy: 1 MeV He+ irradiation experiment

Zhu, Zhenbo; Huang, Hefei; Muránsky, Ondrej; Liu, Jizhao; Zhu, Zhiyong; Huang, Yi

doi:10.1016/j.jnucmat.2020.152694

Cited by 27 publications

(8 citation statements)

References 43 publications

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“…At the same depth, the irradiated sample possessed higher hardness values than the unirradiated one, which suggested the hardening of irradiated Hf1Ta HEA. For the indentation size effect, the hardness decreased slightly with increasing the indentation depth as shown in Figure 10 a, which could be described by the model proposed by Nix and Gao [ 61 ]:

where H represents the measured hardness, H 0 represents the hardness at infinite depth, h* represents a characteristic length which depends on the material and the shape of indenter tips, and h represents the indentation depth.…”

Section: Resultsmentioning

confidence: 72%

“…The average sizes of He bubbles in the conventional materials were summarized in Table 6 . Owing to the limitation of melting point, the temperature of irradiation experiments applied to conventional materials was restricted, which was no more than 973 K. Therefore, the He bubble sizes in the Hf1Ta HEA were larger than those in conventional materials [ 59 , 60 , 61 , 62 , 63 ] due to the higher experiment temperature (1023 K), while He bubble density was one to two orders of magnitude lower. Significantly, the He bubble sizes in the Hf1Ta HEA were between 5–17 nm, which were close to those found in the reported Ti-Zr-Nb-V-Mo [ 46 ] at 1023 K and Ti-V-Nb-Ta RHEAs [ 57 ] at 973 K. However, the average sizes of He bubbles in tens of nanometers (34.1–85.6 nm) were found in FCC-structured NiCoFeCrMn HEAs and its derivatives [ 58 ] at 973 K.…”

Section: Resultsmentioning

confidence: 99%

“…As the plastic zone extended to the lower undamaged region, the measured hardness value could be affected. In this case, the measured hardness value decreased with the increase of depth and finally approached the hardness of the unirradiated area, which was named as softer substrate effect (SSE) [ 61 ]. Therefore, there was a deviation away from linearity when the depth value was large enough (deeper than ~350 nm for the Hf1Ta HEA in this study).…”

Section: Resultsmentioning

confidence: 99%

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He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

Zhang

Wang

et al. 2023

Materials

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High-entropy alloys (HEAs) have shown promising potential applications in advanced reactors due to the outstanding mechanical properties and irradiation tolerance at elevated temperatures. In this work, the novel low-activation Ti2ZrHfxV0.5Ta0.2 HEAs were designed and prepared to explore high-performance HEAs under irradiation. The microstructures and mechanical properties of the Ti2ZrHfxV0.5Ta0.2 HEAs before and after irradiation were investigated. The results showed that the unirradiated Ti2ZrHfxV0.5Ta0.2 HEAs displayed a single-phase BCC structure. The yield strength of the Ti2ZrHfxV0.5Ta0.2 HEAs increased gradually with the increase of Hf content without decreasing the plasticity at room and elevated temperatures. After irradiation, no obvious radiation-induced segregations or precipitations were found in the transmission electron microscope results of the representative Ti2ZrHfV0.5Ta0.2 HEA. The size and number density of the He bubbles in the Ti2ZrHfV0.5Ta0.2 HEA increased with the improvement of fluence at 1023 K. At the fluences of 1 × 1016 and 3 × 1016 ions/cm2, the irradiation hardening fractions of the Ti2ZrHfV0.5Ta0.2 HEA were 17.7% and 34.1%, respectively, which were lower than those of most reported conventional low-activation materials at similar He ion irradiation fluences. The Ti2ZrHfV0.5Ta0.2 HEA showed good comprehensive mechanical properties, structural stability, and irradiation hardening resistance at elevated temperatures, making it a promising structural material candidate for advanced nuclear energy systems.

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Section: Resultsmentioning

confidence: 72%

Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

See 1 more Smart Citation

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

Zhang

Wang

et al. 2023

Materials

Self Cite

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“…The study on nano-grained NiÀ MoÀ Cr alloy was also proposed with irradiation tests by He ion to various dose. [73] Under the same irradiation condition, the smaller volume fraction was found in the proposed HEA films than that in the coarse-grained one, implying a better swelling resistance of the nano-grained HEA. The increase in the hardness of the nano-grained HEA file is more significant than in the coarse-grained alloy, which might be assigned to the impeding effect caused by grain boundaries decorated with He bubbles.…”

Section: Nanocrystalline Metals and Alloysmentioning

confidence: 85%

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

Jiang

et al. 2022

ChemNanoMat

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Interfaces including grain boundaries and heterophase interfaces could withstand the radiation damage via providing sites for trapping the defects. With the urgent demand for high radiation-tolerance nanostructured materials, exploration of the structural properties, especially the role of the interfaces on the radiation response in the nanomaterials, is of significant essentialness in developing the design of new radiation-resistant materials. Herein, the recent progress and development of two main kinds of interfaces, namely the grain boundaries in nanocrystalline and the hetero-phase interfaces in nanolayered materials and nano-composites, in nanostructured materials that are designed for radiation tolerance are summarized. In addition, the radiation response and resistant mechanism under irradiation conditions of the nanocrystalline materials like metals, single-phase alloys, and ceramics, as well as the nanocomposites like nanolayered metals, nanolayered ceramics, metal-carbon nanocomposite, and nanoparticle dispersed steels, are reviewed. Finally, challenges and perspectives are proposed to offer advice for the development of radiation resistance nanomaterials.

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“…The nanohardness and Young's modulus of the irradiated/unirradiated Nb55V25Ta5Si15 REHEA were measured at the peak-damage depths due to the occurrence of the maximum irradiation-induced damage here. In order to ensure statistical significance, the nanohardness [14,16,[48][49][50][51][52][53][54] . This trend suggests that the Nb55V25Ta5Si15 REHEA possesses the superior He-irradiation resistance in comparison with other reported irradiationtolerant alloys, especially under harsh coupling-irradiation environments of the high energy, dose, and temperatures.…”

Section: He-irradiation Behaviors Of the Nb55v25ta5si15 Reheamentioning

confidence: 99%

High-throughput Design of a Lightweight and Ultra-strong Refractory Eutectic High-Entropy Alloy with Outstanding Irradiation Resistance

Liaw

Yang

Wang

et al. 2023

Preprint

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Lightweight, strong, and radiation-tolerant materials are essential for advanced nuclear systems and aerospace applications. However, the current research for these materials mainly focuses on a single design strategy to improve their irradiation resistance via empirical trial-and-error learning. In this study, a novel NbVTaSi refractory eutectic high-entropy alloy was target designed via high-throughput thermodynamic calculations. To exploit the unique eutectic structures of NbVTa and β-Nb5Si3 phases, a new synergistic mechanism for irradiation resistance via balancing inhibition effects on the generation of He-induced lattice defects and the formation and growth of He bubbles was proposed according to the experimental findings and density functional theory calculations. The alloy possesses lightweight (7.4 g/cm3), high yield strengths at room temperature (2.60 GPa) and 850 ℃ (1.84 GPa), and outstanding He-irradiation resistance, superior to other reported radiation-resistant alloys. This study sheds light on the development of future radiation-tolerant materials for advanced nuclear systems and aerospace applications.

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On the irradiation tolerance of nano-grained Ni–Mo–Cr alloy: 1 MeV He+ irradiation experiment

Cited by 27 publications

References 43 publications

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance

High-throughput Design of a Lightweight and Ultra-strong Refractory Eutectic High-Entropy Alloy with Outstanding Irradiation Resistance

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