A5101880990- Fusion materials and technologies
- Nuclear Materials and Properties
- Ion-surface interactions and analysis
- Nuclear materials and radiation effects
- High-Temperature Coating Behaviors
- Hydrogen embrittlement and corrosion behaviors in metals
- Advanced Materials Characterization Techniques
- Advanced battery technologies research
- Advanced materials and composites
- MXene and MAX Phase Materials
- Nonlinear Optical Materials Studies
- Electronic and Structural Properties of Oxides
- Electrocatalysts for Energy Conversion
- Gold and Silver Nanoparticles Synthesis and Applications
- High Temperature Alloys and Creep
- Advanced ceramic materials synthesis
- Supercapacitor Materials and Fabrication
- Nuclear Physics and Applications
- Plasmonic and Surface Plasmon Research
- High Entropy Alloys Studies
State Power Investment Corporation (China)
2021-2023
Peking University
2018-2022
State Key Laboratory of Nuclear Physics and Technology
2019-2022
Abstract The construction of freestanding carbon nanofiber membrane with single‐atomic metal active sites and interconnected microchannels as air electrodes is vital for boosting the performance zinc–air batteries (ZABs). Herein, Fe prepared on hierarchical nitrogen/phosphorus co‐doped nanofibers (Fe SACs@PNCNFs) by loading Fe‐doped zeolitic imidazolate framework‐8 leaf‐like structures electrospun polyacrylonitrile (PAN) subsequent multi‐step pyrolysis in presence sodium monophosphate, which...
In fusion reactors, 14 MeV high-energy neutron irradiation of structural materials will produce large amounts helium and hydrogen simultaneously with displacement defects. These He H atoms interact defects, leading to He-H synergistic effects aggravating the damage. Currently, there exist no available high-flux sources. Additionally, energy spectrum generation in fission reactors or spallation sources greatly differ from those reactors. Multi-ion beam is a promising method emulate induced by...
The development of reliable fusion energy is one the most important challenges in this century. accelerated degradation structural materials reactors caused by neutron irradiation would cause severe problems. Due to lack suitable testing facilities, we have rely on ion experiments test candidate reactors. Moreover, effects are accompanied simultaneous transmutation production helium and hydrogen. One method study He–H synergistic multiple beams (MSIB) that has been studied for decades. To...
Understanding the void swelling dependence on irradiation dose for structural materials is critical design and operation of advanced nuclear reactors. Due to their easy accessibility in high-voltage transmission electron microscopes, beams have been frequently employed investigate mechanisms. Here, we build a general model describe radiation-induced produced by energetic electrons. Based this model, develop quantitative relation between dose, which good agreement with experimental data. By...
To develop advanced nuclear materials, lots of irradiation experiments have been done to various materials in different conditions. Accurate quantification the defects induced by is important for researches especially when evaluating damage caused particles. An model – athermal recombination corrected dpa (arc-dpa) recently introduced. In order apply arc-dpa on experimental data, overall ion and neutron irradiated iron, copper tungsten are calculated based function single cascade PKA energy...
• Micro-nano composite 304L stainless steel (MN304-La) is implanted with He + and annealed at 900 °C. Nano-precipitates, grain boundaries, dislocation are three intrinsic structures coexisting in MN304-La. Three have competing processes for capturing helium bubbles. Nano-precipitates exhibit the strongest strength bubbles compared to boundaries dislocations. The formation migration of lead performance degradation structural materials nuclear reactors. Intrinsic can significantly influence...
Nanostructured materials have great potential for use as structural in advanced nuclear reactors due to the high density of grain boundaries that can serve sinks absorb irradiation-induced defects. In present study, irradiation tolerance a La-doped nanocrystalline 304 austenitic stainless steel (NC-La) with size about 40 nm was investigated under an 6 MeV Au ions 1.5 × 1016 cm-2 at 600 °C and room temperature. Compared its coarse-grained counterpart, no visible voids were observed...
Nanostructured materials are potential candidates for future structural in advanced nuclear reactors. La-doped nanocrystalline 304 austenitic stainless steel (NC304-La) is an nanostructured steel, which excellent small grain size of ~45 nm achieved and stabilized by the doped La element. We carried out irradiation using 3.3 MeV Fe ions to 108 dpa at room temperature 500 °C, then characterized microstructural change NC304-La transmission electron microscopy, scanning microscopy atom probe...
He-H synergistic effects influence the performance of structural materials in fusion reactors. Due to lack high-intensity neutron sources, multiple ion beam irradiation has been widely used as an emulation method study its effects. However, damage rate under is three four orders magnitude higher than that irradiation, and effect on cavity swelling still unclear. In this study, pure nickel was irradiated with single triple beams ~1 displacements per atom (dpa) at 450 °C. The ranged from 1.4 ×...
The manipulation of plasmonics on noble metal nanoparticles (NPs) is great interest in developing nonlinear photonic devices, such as all-optical switches and frequency combs. An [email protected]/Au-shell nanoparticle ([email protected]/Au NP) monolayer proposed for the fine-tuning enhanced third-order nonlinearity. Based different thermodynamic mechanisms Au Y ions, compact core–shell architectures are designed surface-modified fused silica (SiO2) with free electron density, mobility,...
Nanostructured materials are potential candidates for structural in future nuclear reactors. An advanced nanostructured steel - La-doped nanocrystalline austenitic stainless (NC304-La) is reported, which excellent small grain size of ~45 nm achieved and stabilized by the doped La element. Irradiations using 3.3 MeV Fe ions to 108 dpa (displacement per atom) at room temperature (RT) 500℃ were carried out, microstructural evolution NC304-La was characterized transmission electron microscopy,...
Using a high dose Au-ion irradiation and transmission electron microscope, the void swelling in novel bcc reduced activation multi-component alloy FeCrV was investigated. Compared to α-Fe, has stronger suppression effect on swelling, showing narrow distribution of smaller voids. Considering results from aggregation mobile vacancies produced by displacement collisions, migration investigated based ab initio calculations. Migration energies minimum energy paths show after several zigzag steps...