Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Huang, Hefei; Li, D. H.; Li, J. J.; Liu, R. D.; Lei, Guanhong; He, Songnian; Huang, Qing; Liu, Yan

doi:10.2320/matertrans.m2014075

Cited by 36 publications

(9 citation statements)

References 23 publications

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“…4(c). The similar lattice expanding was also observed in Ni 10+ ions irradiated Hastelloy N alloy [23].…”

Section: Gixrd Analysis Of the Lattice Expansion Of Irradiated Samplessupporting

confidence: 81%

“…So the lattice expansion of Hastelloy N alloy under ion irradiation may be attributed to the formation of irradiation-induced defects. [24][25][26] or solute clusters in some literatures [27,28]. For samples irradiated at higher doses of 10 and 27 dpa, many distinguishable dislocation loops with large size can be found, while there are still some black dot defects remaining in the matrix, as shown in Fig.…”

Section: Gixrd Analysis Of the Lattice Expansion Of Irradiated Samplesmentioning

confidence: 76%

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Ion irradiation-induced swelling and hardening effect of Hastelloy N alloy

Zhang

Chen

et al. 2017

Journal of Nuclear Materials

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The volumetric swelling and hardening effect of irradiated Hastelloy N alloy were investigated in this paper. 7 MeV and 1 MeV Xe ions irradiations were performed at room temperature (RT) with irradiation dose ranging from 0.5 to 27 dpa. The volumetric swelling increases with increasing irradiation dose, and reaches up to 3.2% at 27 dpa. And the irradiation induced lattice expansion is also observed. The irradiation induced hardening initiates at low ion dose (≤ 1dpa) then saturates with higher ion dose. The irradiation induced volumetric swelling may be ascribed to excess atomic volume of defects. The irradiation induced hardening may be explained by the pinning effect where the defects can act as obstacles for the free movement of dislocation lines. And the evolution of the defects' size and number density could be responsible for the saturation of hardness. 1 Introduction Molten salt reactor (MSR), one of the generation IV nuclear reactor systems, has received worldwide attention for its high safety, reliability and high efficiency [1]. The structural materials in MSR are confronted with the challenge of the extreme harsh environments, such as high temperature, strong corrosive molten salt and high fluence of neutron irradiation [2]. Hastelloy N alloy has been considered as one of promising structural materials for MSR application thanks to its good

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“…4(c). The similar lattice expanding was also observed in Ni 10+ ions irradiated Hastelloy N alloy [23].…”

Section: Gixrd Analysis Of the Lattice Expansion Of Irradiated Samplessupporting

confidence: 81%

Section: Gixrd Analysis Of the Lattice Expansion Of Irradiated Samplesmentioning

confidence: 76%

Ion irradiation-induced swelling and hardening effect of Hastelloy N alloy

Zhang

Chen

et al. 2017

Journal of Nuclear Materials

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“…According to the finite element simulations as shown in the Appendix, 7.5 M  is almost a constant (independent of h) for conical indenters. The literature value of M ranges from 5 to 10 for Berkovich indenters[7,28,47,48].As the indentation depth h increases gradually, so does the size of the plastic zone under the indenter tip. When the plastic zone is still fully contained inside the irradiated zone, i.e., d RL  ,…”

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confidence: 99%

A mechanistic model for depth-dependent hardness of ion irradiated metals

Xiao

Chen

Yang

et al. 2017

Journal of Nuclear Materials

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A mechanistic model was developed for modeling the depth-dependent hardness in ion irradiated metallic materials. The model is capable of capturing the indentation size effect, ion irradiation induced damage gradient effect, and effect of unirradiated region acting as a soft substrate. A procedure was developed and described in detail to parametrize the model based on experimentally obtained hardness vs. indentation depth curves. Very good agreement was observed between our model predictions and experimental data of several different stainless steels subjected to various ion irradiation conditions. In addition, two hardening mechanisms are revealed in the new model. One is the well-known indentation size effect arising from the creation of geometrically necessary dislocations as the indenter pierces into the materials. The other is the irradiation hardening due to the presence of irradiation-induced defects. As a function of indentation depth h, the hardening due to indentation size effect is described by * hh , while the hardening due to irradiation first follows a power law form n Ph , then changes to 3 Z h Q h  , where * h , P, n , Z and 0 Q  are constants. This transition occurs at the indentation depth when the plastic zone reaches the end of the irradiated layer.

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“…We compared the hardness increments of samples irradiation at RT with those irradiated at 450 °C, and the model developed by Nix-Gao was used to confirm the hardness of the post-irradiated samples [40]. Figure 6b shows that the bi-linearity region with a shoulder is around 220-250 nm, which is approximately 1/5 of the irradiation damage depth, for the samples irradiated at RT and 450 °C; this result reflects the hardness in the region extending down five times of the indenter depth [41]. The average hardness of the irradiated samples was calculated as 4.0 GPa and 3.7 GPa.…”

Section: Hardness Property Analysismentioning

confidence: 89%

Effects of Fe11+ Ions Irradiation on the Microstructure and Performance of Selective Laser Melted 316L Austenitic Stainless Steels

Huan¹,

Li²,

Xiao-dong³

et al. 2020

Metals

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The effect of irradiation temperature on the microstructure, hardness, and corrosion resistance of 316L stainless steels (SS) fabricated by the selective laser melting (SLM) process was investigated to further understand the radiation degradation of the additive manufactured steels. The Transmission Electron Microscopy (TEM) results confirmed the cellular sub-grains and the high-density dislocation networks present in the SLM formed 316L SS. After exposing samples to Fe11+ ions irradiation till 1 dpa at room temperature, the ultra-fine sub-grain structure maintains its configuration, but the dislocations were observed expanding from the vicinity of the sub-grain boundaries into the grains. In contrast, the expanding phenomenon of dislocations was insignificant in samples irradiated at 450 °C. The average size of dislocation loops increased from 6 to 8.5 nm when the irradiation temperature increased, with the number density decreased from 2.7 × 1022/m3 to 1.3 × 1022/m3. This study reveals that the reduced dislocation loop density and distribution region caused by the improved temperature will suppress the radiation hardening and corrosion of SLM 316L SSs.

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Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Cited by 36 publications

References 23 publications

Ion irradiation-induced swelling and hardening effect of Hastelloy N alloy

Ion irradiation-induced swelling and hardening effect of Hastelloy N alloy

A mechanistic model for depth-dependent hardness of ion irradiated metals

Effects of Fe11+ Ions Irradiation on the Microstructure and Performance of Selective Laser Melted 316L Austenitic Stainless Steels

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