Chenyang Lu

ORCID: 0000-0002-3780-8420
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • High-Temperature Coating Behaviors
  • Nuclear Materials and Properties
  • High Entropy Alloys Studies
  • Fusion materials and technologies
  • Ion-surface interactions and analysis
  • Nuclear materials and radiation effects
  • Additive Manufacturing Materials and Processes
  • Advanced Materials Characterization Techniques
  • Metal and Thin Film Mechanics
  • Advanced materials and composites
  • Intermetallics and Advanced Alloy Properties
  • Nuclear reactor physics and engineering
  • Semiconductor materials and devices
  • High Temperature Alloys and Creep
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Microstructure and mechanical properties
  • Advanced Welding Techniques Analysis
  • Cardiac tumors and thrombi
  • Superconductivity in MgB2 and Alloys
  • Mechanical Behavior of Composites
  • Cardiovascular Effects of Exercise
  • Metal Forming Simulation Techniques
  • Metallurgy and Material Forming
  • Mechanical stress and fatigue analysis
  • Hydrogen Storage and Materials

Xi'an Jiaotong University
2019-2024

Soochow University
2023

First Affiliated Hospital of Soochow University
2023

Yangzhou University
2023

University of Michigan–Ann Arbor
2013-2021

Anhui University of Science and Technology
2021

Anhui Science and Technology University
2021

Yunnan University
2017

Northeastern University
2012-2017

Texas A&M University
2016

Abstract A grand challenge in material science is to understand the correlation between intrinsic properties and defect dynamics. Radiation tolerant materials are great demand for safe operation advancement of nuclear aerospace systems. Unlike traditional approaches that rely on microstructural nanoscale features mitigate radiation damage, this study demonstrates enhancement tolerance with suppression void formation by two orders magnitude at elevated temperatures equiatomic single-phase...

10.1038/ncomms13564 article EN cc-by Nature Communications 2016-12-15

A grand challenge in materials research is to understand complex electronic correlation and non-equilibrium atomic interactions, how such intrinsic properties dynamic processes affect energy transfer defect evolution irradiated materials. Here we report that chemical disorder, with an increasing number of principal elements and/or altered concentrations specific elements, single-phase concentrated solid solution alloys can lead substantial reduction electron mean free path orders magnitude...

10.1038/ncomms9736 article EN cc-by Nature Communications 2015-10-28

Recently a new class of metal alloys, single-phase multicomponent composition at roughly equal atomic concentrations (``equiatomic''), have been shown to exhibit promising mechanical, magnetic, and corrosion resistance properties, in particular, high temperatures. These features make them potential candidates for components next-generation nuclear reactors other high-radiation environments that will involve temperatures combined with corrosive extreme radiation exposure. In spite wide range...

10.1103/physrevlett.116.135504 article EN cc-by Physical Review Letters 2016-04-01

A group of single-phase concentrated solid-solution alloys (SP-CSAs), including NiFe, NiCoFe, NiCoFeCr, as well a high entropy alloy NiCoFeCrMn, was irradiated with 3 MeV Ni2+ ions at 773 K to fluence 5 × 1016 ions/cm2 for the study radiation response increasing compositional complexity. Advanced transmission electron microscopy (TEM) energy loss spectroscopy (EELS) used characterize dislocation loop distribution and radiation-induced segregation (RIS) on defect clusters in SP-CSAs. The...

10.1016/j.actamat.2017.01.019 article EN cc-by-nc-nd Acta Materialia 2017-01-12

Energetic ions have been widely used to evaluate the irradiation tolerance of structural materials for nuclear power applications and modify material properties. It is important understand defect production, annihilation migration mechanisms during after collision cascades. In this study, single crystalline pure nickel metal single-phase concentrated solid solution alloys 50%Ni50%Co (NiCo) 50%Ni50%Fe (NiFe) without apparent preexisting sinks were employed study dynamics under ion...

10.1038/srep19994 article EN cc-by Scientific Reports 2016-02-01

The formation mechanism of < 100 > interstitial dislocation loops in ferritic steels stemming from irradiation remains elusive, as their formations are either too short for experiments, or long molecular dynamics simulations. Here, we report on the both and vacancy high energy displacement cascades using large-scale simulations with up to 220 million atoms. Riding supersonic shockwave generated cascade, self-interstitial atoms punched out form only a few picoseconds during one single cascade...

10.1038/s41467-018-07102-3 article EN cc-by Nature Communications 2018-11-13

High- (and medium-) entropy alloys have emerged as potentially suitable structural materials for nuclear applications, particularly they appear to show promising irradiation resistance. Recent studies provided evidence of the presence local chemical order (LCO) a salient feature these complex concentrated solid-solution alloys. However, influence such LCO on their response has remained uncertain thus far. In this work, we combine ion experiments with large-scale atomistic simulations reveal...

10.1073/pnas.2218673120 article EN cc-by-nc-nd Proceedings of the National Academy of Sciences 2023-04-04

Alloying of Ni with Fe or Co has been shown to reduce primary damage production under ion irradiation. Similar results have obtained from classical molecular dynamics simulations 1, 10, 20, and 40 keV collision cascades in Ni, NiFe, NiCo. In all cases, a mix imperfect stacking fault tetrahedra, faulted loops 1/3⟨111⟩ Burgers vector, glissile interstitial 1/2⟨110⟩ vector were formed, along small sessile point defect complexes clusters. Primary reduction occurs by three mechanisms. First,...

10.1063/1.4942533 article EN publisher-specific-oa Journal of Applied Physics 2016-02-25

Abstract The world eagerly needs cleanly-generated electricity in the future. Fusion reactor is one of most ideal energy resources to defeat environmental degradation caused by consumption traditional fossil energy. To meet design requirements fusion reactor, development structural materials which can sustain elevated temperature, high helium concentration and extreme radiation environments biggest challenge for entire material society. Oxide dispersion strengthened steel popular candidate...

10.1038/srep40343 article EN cc-by Scientific Reports 2017-01-12

Atomic disordering in materials alters their physical and chemical properties can subsequently affect performance. In complex ceramic materials, it is a challenge to understand the nature of structural disordering, due difficulty direct, atomic-scale experimental observations. Here we report direct imaging ion irradiation-induced antisite defects Mn+1AXn phases using double CS-corrected scanning transmission electron microscopy provide compelling evidence order-to-disorder phase...

10.1038/s41467-019-08588-1 article EN cc-by Nature Communications 2019-02-07
Coming Soon ...