A5102022200- Fusion materials and technologies
- Nuclear Materials and Properties
- Ion-surface interactions and analysis
- Crystallization and Solubility Studies
- X-ray Diffraction in Crystallography
- High-Temperature Coating Behaviors
- Hydrogen embrittlement and corrosion behaviors in metals
- Metallurgical and Alloy Processes
- Rare-earth and actinide compounds
- Advanced Materials Characterization Techniques
- Magnetic Properties of Alloys
- Nuclear materials and radiation effects
- Metal and Thin Film Mechanics
- Advanced ceramic materials synthesis
- Geophysical and Geoelectrical Methods
- Nuclear Physics and Applications
- Non-Destructive Testing Techniques
- Advanced materials and composites
- Education Systems and Policy
- Innovative Education and Learning Practices
- High Temperature Alloys and Creep
- High voltage insulation and dielectric phenomena
- Hydrogen Storage and Materials
- High Entropy Alloys Studies
- MXene and MAX Phase Materials
Peking University
2017-2023
State Key Laboratory of Nuclear Physics and Technology
2017-2023
Chengdu University of Technology
2011
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...
Abstract Coexistence of hydrogen (H) and helium (He) under vacancy (V) supersaturation in the fusion environment alters dynamic evolution cavities ultimately influences swelling structural materials. Herein, we investigate H–He interaction around a V as one prototype trapping site for H He body-centered cubic (BCC) iron (Fe) utilizing ab initio calculations from thermal dynamics. First, demonstrate significantly stronger He–V than H–V by comparing de-trapping with those He. Furthermore,...
The Vickers hardness test has been widely used for neutron-irradiated materials and nanoindentation ion-irradiated materials. Comparing the nanohardness of same quantitatively establishing a correlation between them is meaningful. In this study, five representative materials—pure titanium (Ti), nickel (Ni), tungsten (W), 304 coarse-grained stainless steel (CG-SS) nanocrystalline austenitic (NG-SS)—are investigated comparison. results show that relationship does not conform to mathematical...
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 ×...
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...