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Symposium 25: Ceramics for Next-Generation Nuclear Energy



Nuclear power is a recognized option to support increasing global energy demand. Materials issues related to expanding nuclear power include performance under extreme conditions, such as elevated temperatures, mechanical stresses, high radiation doses, and corrosive environments. Structural materials and fuels for advanced reactors are critical to future nuclear power as are technologies and materials needed to achieve safe and hazard-free operation. In addition, a more comprehensive understanding of the processes and mechanisms underlying the long-term behavior of materials for nuclear applications is needed. 


This symposium will address topics ranging from materials development for fission and fusion reactors to radiation detection and isotope production. An objective will be to discuss the radiation response of ceramics, glasses, and composite materials to identify linkages and commonalities in their behaviors. In addition, the symposium will address lifetime extension of existing nuclear reactors and the challenges for future nuclear endeavors. Papers are solicited on a wide variety of topics related to materials aspects in nuclear energy using experiment, theory, and simulation.



  • Advancements in nuclear reactor development
  • Accident-tolerant cladding and fuel materials for nuclear energy
  • Engineered materials and design approaches for protective barriers (i.e., fuel cladding, reactor shields, and waste containment)
  • Properties and performance relationships of nuclear materials under extreme conditions (i.e., high radiation dose, elevated temperature, and stress, corrosive environment)
  • Aging and degradation mechanisms and behavior of materials for the fuel cycle, including production and reprocessing
  • Materials properties and design for radiation detection
  • Production of critical isotopes for medical and other applications
  • Materials to enable future nuclear technologies and discovery of applications in the distant future



Jake Amoroso, Savannah River National Laboratory, Jake.amoroso@srs.gov

Josef Matyas, Pacific Northwest National Laboratory

Weon-Ju Kim, Korea Atomic Energy Research Institute, Korea

Yutai Katoh, Oak Ridge National Laboratory, katohy@ornl.gov

Andrew Nelson, Los Alamos National Laboratory

Alexander Gottberg, TRIUMF, Canada

Travis Knight, University of South Carolina

Takashi Nozawa, National Institutes for Quantum and Radiological Science and Technology, Japan

Ming Tang, Los Alamos National Laboratory

Qing Huang, Ningbo Institute of Materials Technology and. Engineering, China

Harlan Brown-Shaklee, Sandia National Laboratories



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