ProgramMaster Logo
Conference Tools for 2021 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Symposium
Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Sponsorship TMS Structural Materials Division
TMS: Composite Materials Committee
TMS: Nuclear Materials Committee
Organizer(s) Anne A. Campbell, Oak Ridge National Laboratory
Dong Liu, University of Bristol
Rick Ubic, Boise State University
Lauren M. Garrison, Oak Ridge National Laboratory
Peng Xu, Westinghouse Electric Company
Johann (Hans) Riesch, Max Planck Institute for Plasma Physics
Scope Composite materials are of growing interest for nuclear fissions and fusion due to their combined excellent physical and mechanical properties that are compatible with extreme radiation and high temperature environments. With the development of next-generation fission reactors and fusion power, materials that can withstand higher neutron flux/thermal load/thermal mechanical stresses and more aggressive environments in terms of oxidation, corrosion/erosion, and tolerance to transmutation elements are required. This requirement makes it necessary to (i) understand the operational limits and degradation mechanisms of existing composite materials and (ii) develop and qualify new materials designs. There is a strong overlap in materials research between fission and fusion in terms materials design, processing, characterisation, and modelling. This symposium aims to bring scientists and engineers together to share ideas and so join the effort in both fields at an international level for the development of these crucial composite materials and to enable collaborations across groups and countries. The design/processing/modelling/joining of the following materials, as well as their physical/mechanical characterisation using ex situ and/or in situ techniques, are encouraged:
• Graphite/carbon based composites for fission and/or fusion (e.g., nuclear graphite, C/C, and novel designs)
• Ceramic-based composites for fusion and/or for nuclear cladding (e,g., SiC-SiC, C/SiC, and novel designs)
• Metal-based composites (e.g., ODS steels, components with protective single- or bi-layer coatings including diamond on fusion components and/or Cr or Cr/Nb on accident-tolerant fuel cladding, tungsten/tungsten composites, laminate systems)
• TRISO fuel (e.g., particles, compacts, and FCM fuel)
Abstracts Due 07/15/2020
Proceedings Plan Undecided
IF YOU WOULD LIKE TO SUBMIT AN ABSTRACT . . .
. . . you are welcome to do so. Just click on the button. Note: To submit an abstract, you must be registered and logged into the system.

Questions about ProgramMaster? Contact programming@programmaster.org