A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation

Jiang, Li; Song, Miao; Yang, Liuqing; Yang, Jingfan; Du, Dongping; Lou, Xiaoyuan; Chen, Youxing

doi:10.1016/j.jnucmat.2021.152946

Cited by 22 publications

(4 citation statements)

References 45 publications

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“…This phenomenon usually happens in deformed metals. [25][26][27] Figure 5B is the HRTEM image of one dislocation wall. In order to observe the dislocation clearly, inverse fast Fourier transform imaging was used, as presented in Figure 5C.…”

Section: Resultsmentioning

confidence: 99%

Full densification of zirconium carbide ceramics sintered under high pressure at low temperature

Zou

et al. 2021

Int J Applied Ceramic Tech

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Zirconium carbide (ZrC) ceramic is one of the most important and promising materials with a high melting point. However, its low diffusion coefficient affects its densification behavior, which dramatically limits its engineering application. For polycrystal ceramic materials, sintering by thermal diffusion is the most widely used method for consolidation. But in view of the difficult densification behavior of ZrC, it is necessary to develop new sintering methods together with another driving force. In the study, we reported an ultra-high-pressure sintering strategy to fully densify ZrC ceramic under 1.7 GPa at 1600°C. The sintered sample exhibited high density, fine grain size, excellent mechanical properties, and a large number of crystal defects, including dislocation networks and walls, which were similar to those in deformed metals. Its hardness increased to 2057.44 HV0.1 because of its unique microstructure.

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Section: Resultsmentioning

confidence: 99%

Full densification of zirconium carbide ceramics sintered under high pressure at low temperature

Zou

et al. 2021

Int J Applied Ceramic Tech

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“…Combining the advantages of the SLM process with the conventional structural materials used in nuclear systems, the SLM 316L stainless steel was proposed with great potential in nuclear applications [7][8][9][10][11]. On one hand, the excellent performance of strength and ductility in SLM 316L has been verified, which is attributed to the unique cellular dislocation structures frequently reported in AM Fe-based alloys [12].…”

Section: Introductionmentioning

confidence: 99%

The Mechanisms of Inhibition Effects on Bubble Growth in He-Irradiated 316L Stainless Steel Fabricated by Selective Laser Melting

et al. 2023

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The AISI 316L austenitic stainless steel fabricated by selective laser melting (SLM) is considered to have great prospects for applications in nuclear systems. This study investigated the He-irradiation response of SLM 316L, and several possible reasons for the improved He-irradiation resistance of SLM 316L were systematically revealed and evaluated by using TEM and related techniques. The results show that the effects of unique sub-grain boundaries have primary contributions to the decreased bubble diameter in SLM 316L compared to that in the conventional 316L counterpart, while the effects of oxide particles on bubble growth are not the dominant factor in this study. Moreover, the He densities inside the bubbles were carefully measured using electron energy loss spectroscopy (EELS). The mechanism of stress-dominated He densities in bubbles was validated, and the corresponding reasons for the decrease in bubble diameter were freshly proposed in SLM 316L. These insights help to shed light on the evolution of He bubbles and contribute to the ongoing development of the steels fabricated by SLM for advanced nuclear applications.

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“…Carter and coworkers observed irradiation hardening associated with uniform Ni-Mn-S-P clustering in both the bainite and ferrite phases, whereas Gasparrini and coworkers attributed considerable hardening to bubble/void formation. Finally, Jiang, et al investigated void swelling in additively manufactured 316L stainless steel treated with HIP, under ion irradiation to 100 dpa at various temperatures [16]. They found that the HIP specimens display a longer incubation period before void swelling as compared to non-HIP counterparts [16].…”

Section: Introductionmentioning

confidence: 99%

“…Finally, Jiang, et al investigated void swelling in additively manufactured 316L stainless steel treated with HIP, under ion irradiation to 100 dpa at various temperatures [16]. They found that the HIP specimens display a longer incubation period before void swelling as compared to non-HIP counterparts [16]. These studies present inconclusive and widely differing findings on PM-HIP irradiation response; thus, further investigation is warranted.…”

Section: Introductionmentioning

confidence: 99%

Comparing Structure-Property Evolution for Pm-Hip and Forged Alloy 625 Irradiated with Neutrons to 1dpa

et al. 2022

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A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation

Cited by 22 publications

References 45 publications

Full densification of zirconium carbide ceramics sintered under high pressure at low temperature

Full densification of zirconium carbide ceramics sintered under high pressure at low temperature

The Mechanisms of Inhibition Effects on Bubble Growth in He-Irradiated 316L Stainless Steel Fabricated by Selective Laser Melting

Comparing Structure-Property Evolution for Pm-Hip and Forged Alloy 625 Irradiated with Neutrons to 1dpa

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