Surface damages of polycrystalline W and La2O3-doped W induced by high-flux He plasma irradiation

Liu, Lu; Li, Shou-Zhe; Liu, Dongping; Benstetter, Günther; Zhang, Yang; Hong, Yi; Fan, Hongyu; Ni, Weiyuan; Qi, Yang; Wu, Yunfeng; Bi, Zhenhua

doi:10.1016/j.jnucmat.2018.01.047

Cited by 14 publications

(3 citation statements)

References 45 publications

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“…Additionally, quite a lot of questions remain concerning the description of the kinetics and mechanisms of radiation damage caused by the accumulation of helium in the structure of the near-surface layer, which can occur in the case of high-temperature nuclear reactors and thermonuclear reactors, both as a result of transmutation reactions and upon interaction with coolants [28][29][30]. In this regard, it is necessary to have a clear understanding of the processes that occur during the accumulation of helium, as well as the consequences they have on changes in the structural, strength, or mechanical properties of structural materials.…”

Section: Introductionmentioning

confidence: 99%

Study of Helium Swelling and Embrittlement Mechanisms in SiC Ceramics

et al. 2022

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This work is devoted to the study of the radiation damage kinetics and subsequent embrittlement of the near-surface layer of SiC ceramics subjected to irradiation with low-energy He2+ ions. Interest in these types of ceramics is due to their great prospects for use as structural materials for nuclear power, as well as for use in the creation of protective structures for long-term storage of spent nuclear fuel. During the study, the dependences of changes in the structural, mechanical, strength, and morphological characteristics of SiC ceramics depending on irradiation fluence were obtained. It has been established that the greatest changes in the strength properties are associated with the dominance of the crystal lattice swelling effect in the structure due to an increase in the concentration of implanted helium, and its further agglomeration with the formation of vacancy complexes of the He-V type. A model for changing the structural properties of ceramics irradiated with low-energy He2+ ions based on the change in the contributions of the dislocation density concentration, anisotropic distortion of the crystal lattice, and the effect of swelling as a result of implantation is proposed.

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Section: Introductionmentioning

confidence: 99%

Study of Helium Swelling and Embrittlement Mechanisms in SiC Ceramics

et al. 2022

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“…Therefore, it is imperative to seek new materials with outstanding physical and chemical performances as alterna-tive materials to withstand the harsh fusion environments in the future. Dispersion strengthened alloys have attracted more attention and been proposed as the hopeful alternative due to their better ductility, more excellent mechanical properties, and lower DBTT than pure W, as well as reduced hardening and embrittlement [13][14][15][16]. Recently, it has been reported that dispersing a small amount of thermal-stable carbide (e.g.…”

Section: Introductionmentioning

confidence: 99%

Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma

et al. 2021

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Surface blistering and deuterium (D) retention behaviors in pure tungsten (W) and 0.5 wt% ZrC-doped W alloy (WZC) exposed to D plasma have been investigated as a function of incident D fluence up to 2.6 × 1025 D m−2. Surface observations show that large-sized blisters (∼8–10 μm) and a few small blisters (<2 μm) are formed on the W samples. For WZC, the surface of the samples is covered by a high density of small blisters (<1 μm), and no blister larger than 2 μm is found. Cross section views show that the large-sized blisters originate from subsurface grain boundaries, and the small blisters originate from intra-granular cavities at depths much closer to the surface. The intra-granular blisters are preferentially formed on the grains with a normal direction close to [111] for both types of sample. The inter-granular blisters formed in pure W are significantly suppressed in WZC, and the fluence threshold for blister formation in WZC is lower than that in W. The D depth distributions indicate that the implanted D is mainly retained in the near-surface region of WZC and W. Besides, a higher and broader D peak is observed at a depth of between 0.1–0.25 μm in WZC, but the intensity and width of the D peak is lower and thinner in W. The desorption spectra of WZC shift to the lower temperature side as compared to W, and the total retained D amount in WZC and W is comparable in the fluence range of 2.8 × 1024–2.6 × 1025 D m−2.

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“…Besides, a few studies researched that introducing secondary phase could eliminate the defects of the Tungsten www.springer.com/42864 SLM sample and improve its mechanical properties. Some oxides and carbides were often introduced as the second phase [29][30][31][32][33][34][35][36][37][38] for improving plasticity and thermal shock resistance. At present, studies have shown that adding a carbide reinforcement in the SLM process can capture oxygen impurities to enhance the grain boundary strength and reduce cracks [39][40][41].…”

Section: Introductionmentioning

confidence: 99%

Selective laser melting of lanthanum oxide-reinforced tungsten composites: microstructure and mechanical properties

Wei

et al. 2021

Tungsten

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In this study, La 2 O 3 nanoparticles were introduced into the tungsten (W) matrix to optimize the microstructure and properties of pure W. The W-La 2 O 3 composites with different mass ratios of La 2 O 3 were manufactured by selective laser melting (SLM). The result showed that the average grain sizes for W-1 wt% La 2 O 3 and W-2 wt% La 2 O 3 were reduced by more than 51.3% compared with that of pure W, and the defects obviously decreased. The microhardness and compressive strength of the SLM W-2 wt% La 2 O 3 sample reached 455 HV and 2194 MPa, respectively. The toughness of the SLM W-2 wt% La 2 O 3 sample also improved significantly. One main reason was that the La 2 O 3 nanoparticles provide many heterogeneous nucleation sites to refine the grains. The other main reason was that La 2 O 3 nanoparticles formed into dislocation loops, which hindered the movement of dislocations and then increased the strength further. This research provided a new method to improve the mechanical properties of SLM W by introducing La 2 O 3 nanoparticles to achieve fine-grains strengthening and Orowan strengthening.

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Surface damages of polycrystalline W and La2O3-doped W induced by high-flux He plasma irradiation

Cited by 14 publications

References 45 publications

Study of Helium Swelling and Embrittlement Mechanisms in SiC Ceramics

Study of Helium Swelling and Embrittlement Mechanisms in SiC Ceramics

Surface blistering and deuterium retention behaviors in pure and ZrC-doped tungsten exposed to deuterium plasma

Selective laser melting of lanthanum oxide-reinforced tungsten composites: microstructure and mechanical properties

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