April 17 - 21, 2017
Phoenix, Arizona
2017 MRS Spring Meeting

Symposium ES5-Advances in Materials, Experiments and Modeling for Nuclear Energy

Understanding materials behavior in extreme environments is the centerpiece in the development of next-generation nuclear reactors. High radiation flux, thermal and chemical gradients, and corrosive environments cause significant degradation in the chemical and mechanical properties of materials. Overcoming technological challenges such as enhanced radiation resistance of reactor core structures and nuclear fuel materials at high doses accompanied with longer lifetimes and improved safety are needed for current and future nuclear reactors. These challenges require design and development of new and advanced materials using a multiscale understanding, i.e., from electronic to microstructure evolution, anchored by advancements in experimental characterization techniques, and predictive modeling capabilities.

While broadly focusing on the progresses in the understanding of materials behavior in extreme environments, this symposium will also summarize recent advancements in experimental characterization techniques, multiscale modeling methodologies, and materials development for nuclear-reactor applications.

Topics will include:

  • Novel materials development, including high entropy alloys
  • Thermal, chemical and mechanical properties of materials
  • Materials behavior under extreme environments – radiation, corrosion, stress and temperature, including phase stability, fuel-clad interactions, fission product behavior
  • Materials improvements in nanostructured and heterointerfacial materials
  • Multiscale modeling and simulation, including new methods to bridging different length and time scales
  • Novel characterization techniques of materials behavior under irradiation, stress, in-situ methods

Invited Speakers:

  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _0 (University of Lilles, France)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _1 (CEA-Saclay, France)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _2 (Georgia Institute of Technology, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _3 (University of Tennessee, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _4 (Argonne National Laboratory, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _5 (Australian Nuclear Science and Technology Organisation, Australia)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _6 (University of California, Los Angeles, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _7 (University of Wisconsin-Madison, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _8 (Japan Atomic Energy Research Institute, Japan)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _9 (Drexel University, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _10 (Los Alamos National Laboratory, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _11 (University of Michigan, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _12 (Westinghouse Electric Company, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _13 (Oak Ridge National Laboratory, USA)
  • ES5_Advances in Materials, Experiments and Modeling for Nuclear Energy _14 (Idaho National Laboratory, USA)

Symposium Organizers

Dilpuneet Aidhy
University of Wyoming
Department of Mechanical Engineering
USA

Kazuto Arakawa
Shimane University
Japan

Estelle Meslin
CEA – Saclay
France

Haixuan Xu
University of Tennessee
Department of Materials Science and Engineering
USA

Topics

defects diffusion elastic properties grain boundaries microstructure radiation effects simulation strain relationship thermal conductivity transmission electron microscopy (TEM)