A5100757236- Advanced ceramic materials synthesis
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear reactor physics and engineering
- Heat Transfer Mechanisms
- Advanced materials and composites
- Turbomachinery Performance and Optimization
- Nuclear Physics and Applications
- Nuclear materials and radiation effects
- Aluminum Alloys Composites Properties
- Diamond and Carbon-based Materials Research
- Nuclear and radioactivity studies
- Combustion and flame dynamics
- Gas Sensing Nanomaterials and Sensors
- ZnO doping and properties
- Advanced Photocatalysis Techniques
- Radioactive element chemistry and processing
- Heat transfer and supercritical fluids
- Microwave Dielectric Ceramics Synthesis
- Fiber-reinforced polymer composites
- Semiconductor materials and devices
- Mesoporous Materials and Catalysis
- Electrowetting and Microfluidic Technologies
- Electrical and Thermal Properties of Materials
- Catalytic Processes in Materials Science
Tsinghua University
2014-2024
State Key Laboratory of New Ceramics and Fine Processing
2017-2024
Chongqing University of Science and Technology
2024
Beijing University of Technology
2024
Nanjing University of Aeronautics and Astronautics
2022-2024
Key Laboratory of Nuclear Radiation and Nuclear Energy Technology
2016-2020
East China University of Technology
2019-2020
Central South University
2018
Suzhou University of Science and Technology
2018
Changsha Mining and Metallurgy Research Institute (China)
2012
Compact and uniform zirconium carbide (ZrC) coatings have been successfully deposited on coated fuel particles using a ZrCl 4 +H 2 +Ar+C 3 H 6 gas mixture. Zirconium tetrachloride (ZrCl ) powder feeder was especially designed manufactured to control accurately the flow rate of produce ZrC an industrial scale. The coating has large density (6.57 g/cm ), thickness 35 μm, stoichiometry close Zr/C=1, clear interface between substrate. exhibits fcc ‐ZrC phase with grain size 11.18 nm (111)...
Abstract A dual layer silicon carbide (SiC) coating including inner porous SiC ( p ‐SiC) and outer dense d was fabricated on the matrix graphite (MG) spheres of high‐temperature gas‐cooled reactor fuel elements by pack cementation fluidized‐bed chemical vapor deposition process to improve oxidation‐resistant property. Microstructure demonstrates different density structure two layers with no obvious boundaries between them. Weight gain curves oxidation tests at 1773 K for 200 hours show that...
A micro four‐layer SiC coating, which includes inner transition layer, fine‐grained dense bulk and outer loose was fabricated on the matrix graphite spheres of high‐temperature gas‐cooled reactor fuel elements to improve oxidation‐resistant property by a two‐step pack cementation process. According experiment results, can be differentiated grain size microstructure variation. The oxidation tests at 1773 K for 200 h reveal that coating structure could effectively resistance with weight gain...
A nonuniform distribution of tristructural isotropic (TRISO) particles within a high-temperature gas-cooled reactor (HTGR) pebble may lead to excessive thermal gradients and expansion during operation. If the are closely clustered, local hotspots form, leading stresses on particle layers an increased probability failure. Although X-ray digital radiography (DR) is currently used evaluate TRISO distributions in pebbles, DR projection images two-dimensional nature, which would potentially miss...
Nonuniform distribution of tri-structural-isotropic (TRISO) fuel particles in a spherical element (SFE) may increase the failure probability SFE high-temperature gas-cooled reactor, leading to release fission products. To evaluate uniformity TRISO nondestructively, 3-dimensional cone-beam computed tomography is used image SFE, and are segmented. After particle positions identified, Voronoi tessellation Delaunay triangulation extract several geometric metrics. Results indicate that both...