The next generation nuclear energy plays a crucial role in the development of a sustainable and decarbonization for fission and fusion. Many of the critical structural components inside a next generation nuclear energy system will be subjected to a harsh application environment including high temperature, high energy and high 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 solution for achieving higher fuel burning rate and efficiency, improved economic benefits, an inherently safe reactor with long-term stability, and immobilization of radiation nuclear 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 symposium is to provide a forum for materials scientists and nuclear engineers from around the world to share their up-to-date progress and exchange views on the development of various advanced materials for next-generation nuclear energy and application experiences of these materials in the design of reactors, fuels, and waste treatment. Novel approaches utilizing artificial intelligence, including machine learning and deep learning, in materials design, testing, and system advancements are encouraged.
Proposed sessions and topics of interest:
- Advanced ceramics, ceramic composites, and graphite materials for advanced fission and fusion nuclear energy systems
- Radiation effects and damages on microstructure and mechanical properties
- Materials and their behaviors under the accidental conditions
- Next-generation accident-tolerant fuels
- Molten salt, lead, or supercritical water corrosion
- Computer simulation of radiation effect, materials modeling, and database
- Ceramics and glass for nuclear waste management
Symposium organizers
- Xiao-Ying Yu, Oak Ridge National Laboratory, USA; yuxiaoying@ornl.gov
- Guo-Jun Zhang, Donghua University, China; gjzhang@dhu.edu.cn
- Ji-Yeon Park, Korea Atomic Energy Research Institute, Korea; jypark@kaeri.re.kr
- Yutai Katoh, Oak Ridge National Laboratory, USA
- Hua-Tay Lin, Guangdong University of Technology, China
- Young-Wook Kim, University of Seoul, Korea
- Houzheng Wu, SIAMC Advanced Material Corporation, China
- Yingjie Zhang, Australian Nuclear Science and Technology Organization, Australia
- Libin Sun, Tsinghua University, China
- Hans J. Seifert, Karlsruhe Institute of Technology, Germany
- Jia-Xiang Xue, China Nuclear Power Technology Research Institute Co., Ltd., China
- Tatsuya Hinoki, Kyoto University, Japan
- Monica Ferraris, Politecnico di Torino, Italy
- Ping Xiao, The University of Manchester, United Kingdom
- Haibin Zhang, China Academy of Engineering Physics, China
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