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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
Sponsorship TMS Structural Materials Division
TMS: Advanced Characterization, Testing, and Simulation Committee
TMS: Nuclear Materials Committee
Organizer(s) Yi Xie, Purdue University
Miaomiao Jin, Pennsylvania State University
Jason M. Harp, Oak Ridge National Laboratory
Fabiola Cappia, Idaho National Laboratory
Jennifer K. Watkins, Idaho National Laboratory
Michael R. Tonks, University of Florida
Scope Fuel and fuel-cladding interaction constitute the key to understanding fuel performance. The combined effect of microstructural evolution and chemical change cause loss of performance in various forms such as embrittlement, deformation, phase instability, etc, which need to be well understood to enable materials evaluation and prediction in normal and accident scenarios. The designs of current and next-generation reactors are varied. The types of fuels include ceramic, metal, and composite fuels, including UO2-, UN-, U3Si2-, U-Zr-, U-Mo-based, and TRISO. There are also multiple types of cladding materials in use/consideration, e.g., zircoloy, stainless steels, SiC/SiC composite, ODS, HEA concepts and coating, made by various advanced manufacturing methods. In particular, the confounding factors from chemically active fission products (lanthanides, tellurium, etc.) and impurities (oxygen, carbon, etc.) can complicate the fuel performance analysis, due to the changes in fuel and fuel-cladding interaction. This symposium aims to bring together experimental and computational investigations that assist in understanding the microstructural, mechanical, and chemical changes in these solid fuels and fuel-cladding interfaces. Both the synergistic and separate effects of involved physical processes, with fresh or certain burn-up or surrogate fuels, are of interest. Analysis of advanced fuel types and cladding concepts are strongly encouraged. This symposium also calls for multi-scale modeling and simulations and fuel performance modeling.

The topics of interest include experimental and modeling efforts in the following aspects, but not limited to:

• Evolution of defects, microstructure, and phase in fuels or fuel surrogates
• Impact of impurities on microstructure and phase transformation of fuels or fuel surrogates
• Behaviors of fission products in fuels and/or cladding
• Fuel-cladding mechanical and chemical interactions
• Advanced manufacturing and characterization technologies for nuclear fuels

Abstracts Due 07/01/2022
Proceedings Plan Undecided
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