Special Symposia

Several special symposia will be organized during CICC-10. If you want to attend one of the following special symposia, please submit your abstract directly to ccs-cicc@vip.163.com, the secretariat of CICC-10.

Symposium A: Virtual Materials Design and Ceramic Genome
Symposium B: UHTC & MAX Phase Workshop 2017
Symposium C: Advanced Materials for Next Generation Nuclear Energy
Symposium D: Progress and Challenges in Lead-free Piezoelectrics
Symposium E: 先进陶瓷制备技术与产业化应用 (中文会场)
Symposium F: Geopolymer and Geopolymer Developed Ceramics & Composites

 
 

 

Symposium C
Advanced Materials for Next Generation Nuclear Energy

The next generation nuclear energy, including fission & fusion energy systems, plays a crucial role in the development of a sustainable and low-carbon society. Many of the critical structural components inside a next generation nuclear energy system will be subjected to a harsh application environment including high temperature, intense and higher flux neutron radiation, and chemical corrosion by coolants, which likely impose a grand challenge for most incumbent metallic materials. Advanced materials based on inorganic nonmetallic materials are expected to provide a range of material solutions for achieving higher fuel burning rate and efficiency, improved economic benefits, an inherently safe reactor with long-term stability, and immobilization of radiation wastes. Currently, the incorporation of advanced ceramics would allow engineers to design a nuclear fuel system that would be more accident tolerant during the loss of cooling system as compared to the UO2-Zircalloy system currently employed for light water and pressurized water reactors. Fine-grained graphite and ceramic-based composites have been widely considered for structural components in various high temperature reactors (HTR). On the other hand, advanced ceramic materials could have the potential to advance radiation detection and secure waste immobilization technologies. Therefore, the aim of this workshop is to provide an open forum for materials scientists and nuclear engineers from around the world to share their views and up-to-date progress on the development of various advanced materials for next generation nuclear energy and application experiences of these materials in design of reactors, fuels, and waste treatment.

Proposed topics
SC1. Design, synthesis and properties of potential advanced ceramics, ceramic composites and graphite materials for next generation nuclear energy
SC2. Newly emerging materials for nuclear energy
SC3. Ion, proton and neutron irradiation effect on structures and properties of advanced ceramics, ceramic composites and graphite materials
SC4. Ceramics for accident-tolerant fuels, reactor cores, and water and irradiation resistant coatings
SC5. Molten salt, lead, or supercritical water corrosion of advanced ceramics, ceramic composites and graphite materials
SC6. Computer simulation of irradiation effect resistance of advanced ceramics, ceramic composites and graphite materials
SC7. Microstructure characterization of advanced ceramics, ceramic composites and graphite materials under irradiation environment
SC8. Standardization and qualification of ceramic components of nuclear reactors

Symposium Organizers
Hua-Tay Lin, Guangdong University of Technology, China
Guo-Jun Zhang, Donghua University, China
Haibin Zhang, China Academy of Engineering Physics, China
Monica Ferraris, Politecnico di Torino, Italy
Yutai Katoh, Oak Ridge National Laboratory, USA
Shaoming Dong, Shanghai Institute of Ceramics, CAS, China
Hisayuki Suematsu, Nagaoka University of Technology, Japan
Hans J. Seifert, Karlsruhe Institute of Technology, Germany
Changheui Jang, Korea Advanced Institute of Science and Technology, Korea
Houzheng Wu, Loughborough University, UK
Jingyang Wang, Institute of Metal Research, Chinese Academy of Science, China
Yujin Wang, Harbin Institute of Technology, China
Ji Zou, University of Brimingham, UK
Zhiguang Wang, Institute of Modern Physics, CAS, China
Shi-Kuan Sun, University of Sheffield, UK
Liqun Shi, Fudan University, China

Point of Contact
Dr. Guo-Jun Zhang (gjzhang@dhu.edu.cn)
Dr. Haibin Zhang (wsschbinzhang@163.com)