Research

1.The Physics and Chemistry of Carbon.

Current research primarily focuses on: (1) liquid-phase carbonization theory, the structure and properties of mesophase pitch, (2) thermal properties of graphite, and (3) the formation and evolution of irradiation defects in graphite crystals. Previous research findings have been published in journals such as Carbon and Fuel.

2.High-Purity Carbon Materials.

Research work includes: (1) high-temperature purification mechanisms of carbon materials, reaction mechanisms of impurities with halogen free radicals, (2) preparation of high-purity isostatic graphite, (3) preparation of high-purity viscose-based carbon fiber felt for photovoltaic and semiconductor applications, and (4) preparation of high-purity natural flake/microcrystalline graphite. Research results have been published in journals such as Carbon and Journal of Nuclear Materials.

3.Preparation Technology of Artificial Graphite and Isostatic Graphite.

Isostatic graphite is a classic structural material widely used in photovoltaics, machinery, aerospace, and nuclear energy fields. Building on the carbon materials specialty of Hunan University, the following research has been conducted: (1) preparation technology of fine-structure isostatic graphite, (2) preparation of isotropic graphite with a low coefficient of thermal expansion, (3) porous graphite materials, and (4) graphite/ceramic composites. Research findings have been published in journals such as Carbon and Journal of Nuclear Materials.

4.Structural Characterization and Performance Evaluation of Nuclear-Grade Graphite for High-Temperature Gas-Cooled Reactors.

Nuclear-grade graphite is a core structural material for high-temperature gas-cooled reactors, forming one of the fundamental substances on which high-temperature reactors are built. Its irradiation performance determines the lifespan of high-temperature reactors; hence, improving graphite performance equates to enhancing reactor performance. Evaluating and characterizing the performance and structure of nuclear-grade graphite will provide a basis for reactor core design and establish a theoretical foundation for predicting graphite behavior within reactors. Research includes: (1) characterization of the multi-scale microstructure of nuclear-grade graphite, (2) friction and wear properties of nuclear-grade graphite, (3) mechanical properties of nuclear-grade graphite, and (4) graphite matrix and its modification for spherical fuel elements in high-temperature gas-cooled reactors. Previous research results have been published in Carbon, Journal of Nuclear Materials, Nuclear Engineering and Design, and other journals.

5. Theory and Application of Other Carbon Materials.

a. Deep processing of natural graphite.

b. Application of carbon materials in the thermoelectric field, recruiting master’s students for a joint training program between the School of Materials Science and Engineering, Hunan University, and the Shanghai Institute of Ceramics, Chinese Academy of Sciences

c. Carbon materials for energy storage.

Research Highlights and Gallery