About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Ceramics and Ceramic-based Composites for Nuclear Fission Applications
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Presentation Title |
Analyzing ZrN and LiF-doped ZrN as a Shield Material for Fusion and Space Reactors |
Author(s) |
Mediha Merve Karatas, Steven John Zinkle |
On-Site Speaker (Planned) |
Mediha Merve Karatas |
Abstract Scope |
ZrN is a promising candidate matrix material for high performance composite radiation shields for nuclear energy systems, due to its low H isotope permeation, high thermal conductivity, high melting point and high thermodynamic stability. LiF doping was used to investigate possible sintering enhancement due to the creation of Schottky vacancies in divalent ZrN from monovalent LiF impurity. Spark Plasma Sintering (SPS) at different sintering temperatures was used to obtain fully dense bulk material. Characterization of the sintered ZrN and LiF-doped ZrN samples was performed using Raman spectroscopy and electron microscopy. Electron backscatter diffraction (EBSD) was used to investigate the grain size versus sintering conditions. Transmission electron microscopy (TEM) and electron energy loss spectroscopy (EELS) were performed on focused ion beam liftouts in order to investigate the LiF spatial distribution. Modeling results on hydrogen isotope permeation and dissociation of H-containing particles in the composite shield containing YH2 particles will be presented. |
Proceedings Inclusion? |
Planned: |
Keywords |
Ceramics, Characterization, Nuclear Materials |