Jian Zhang

Dr. Jian Zhang


Research Focus & Metrics

Academic Career Length

8Years (2019-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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25 April 2023 in Acta Materialia
Verified
Journal Article
Closed access
YBYi-Nan Bian
Yi-Nan Bian
YLYan Lu
Yan Lu
JZJian Zhang
Jian Zhang
BGBin Gao
Bin Gao
WWWen-Bin Wang
Wen-Bin Wang
Weizhong HanWeizhong Han
Weizhong Han

2 January 2025 in Journal of Applied Physics
Verified
Journal Article
Open access
ZZZijun Zhang
Zijun Zhang
SJShengming Jiang
Shengming Jiang
XHXiaotian Hu
Xiaotian Hu
JZJian Zhang
Jian Zhang
Silicon carbide and its derivatives are promising materials with potential applications in various types of nuclear reactors. To better understand their characteristics, this paper investigates the recrystallization behavior of amorphous SiC prepared through pre-irradiation using 800 keV Kr2+. Following different annealing processes, Raman spectra revealed that recrystallization happened beyond 873 K, and nearly complete recrystallization of the amorphous layer occurs at 1423 K. Afterward, in situ annealing and He+ irradiation experiments were conducted. The results indicate that the recrystallization progress is a layer-by-layer epitaxial regrowth on the amorphous–crystal interface under 873 K annealing, and the epitaxial recrystallization would slow down mainly due to the accumulation of defects and Kr atoms. However, under 30 keV He+ irradiation at 873 K, the interface continues to move. Moreover, when the irradiation dose rises, nanocrystals and helium bubbles appear simultaneously, growing in both size and density. The different recrystallization behaviors caused by irradiation and non-irradiation conditions could be explained by radiation-enhanced atomic diffusion, and helium bubbles are likely to be the by-products of nanocrystal formation. A possible explanation is proposed. This study provides insights into the practical application of amorphous silicon carbide in reactors and other irradiation environments.

2 November 2022 in Journal of Nuclear Materials
Verified
Journal Article
Closed access
XHXiaotian Hu
Xiaotian Hu
SJShengming Jiang
Shengming Jiang
TFTing Feng
Ting Feng
ZHZijing Huang
Zijing Huang
SDShigang Dong
Shigang Dong
JZJian Zhang
Jian Zhang

26 June 2023 in Materials
Verified
Journal Article
Open access
PDF file
XLXing Liu
Xing Liu
ZDZhi Dong
Zhi Dong
SSShangkun Shen
Shangkun Shen
YWYu Wang
Yu Wang
ZWZefeng Wu
Zefeng Wu
Engang FuEngang Fu
Engang Fu
Tungsten (W), as a promising plasma-facing material for fusion nuclear reactors, exhibits ductility reduction. Introducing high-density coherent nano-dispersoids into the W matrix is a highly efficient strategy to break the tradeoff of the strength–ductility performance. In this work, we performed helium (He) ion irradiation on coherent oxide-dispersoids strengthened (ODS) W to investigate the effect of coherent nanoparticle interfaces on the behavior of He bubbles. The results show that the diameter and density of He bubbles in ODS W are close to that in W at low dose of He ion irradiation. The radiation-induced hardening increment of ODS W, being 25% lower than that of pure W, suggests the involvement of the coherent interface in weakening He ion irradiation-induced hardening and emphasizes the potential of coherent nano-dispersoids in enhancing the radiation resistance of W-based materials.

24 May 2023 in Materials
Verified
Journal Article
Open access
PDF file
SSShangkun Shen
Shangkun Shen
ZSZhangjie Sun
Zhangjie Sun
LHLiyu Hao
Liyu Hao
XLXing Liu
Xing Liu
JZJian Zhang
Jian Zhang
Engang FuEngang Fu
Engang Fu
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.

2 July 2021 in Materials
Verified
Journal Article
Open access
PDF file
HHHuanhuan He
Huanhuan He
ZLZhiwei Lin
Zhiwei Lin
SJShengming Jiang
Shengming Jiang
XHXiaotian Hu
Xiaotian Hu
JZJian Zhang
Jian Zhang
ZHZijing Huang
Zijing Huang
The FeCoNiCrTi0.2 high-entropy alloys fabricated by vacuum arc melting method, and the annealed pristine material, are face centered cubic structures with coherent γ’ precipitation. Samples were irradiated with 50 keV He+ ions to a fluence of 2 × 1016 ions/cm2 at 723 K, and an in situ annealing experiment was carried out to monitor the evolution of helium bubbles during heating to 823 and 923 K. The pristine structure of FeCoNiCrTi0.2 samples and the evolution of helium bubbles during in situ annealing were both characterized by transmission electron microscopy. The annealing temperature and annealing time affect the process of helium bubbles evolution and formation. Meanwhile, the grain boundaries act as sinks to accumulate helium bubbles. However, the precipitation phase seems have few effects on the helium bubble evolution, which may be due to the coherent interface and same structure of γ’ precipitation and matrix.