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  5. Corrosion and Microstructural Characterization of Molybdenum-YSZ Cermets Following Hydrogen Exposure up to 2630 K
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Corrosion and Microstructural Characterization of Molybdenum-YSZ Cermets Following Hydrogen Exposure up to 2630 K

Date Issued
May 1, 2022
Author(s)
Duffin, Taylor G  
Advisor(s)
Steven J. Zinkle
Additional Advisor(s)
David Donovan
Lawrence Heilbronn
Richard Howard
Richard Wood
Permanent URI
https://trace.tennessee.edu/handle/20.500.14382/28432
Abstract

Ceramic-metallic (cermet) fuels are a promising fuel type for outer space nuclear thermal propulsion (NTP). A key feasibility issue is the hydrogen chemical compatibility of candidate fuels in the proposed extreme operating temperatures for NTP systems (> 2500 K). In this study, molybdenum matrix cermets containing 40–70 vol% yttria stabilized zirconia (YSZ) particles (as a surrogate for ceramic fuel particles) were produced via spark plasma sintering (SPS) and exposed to flowing hydrogen at high temperature (2000–2630 K). Both steady state and thermally cycled (4 cycles with intermediate cooling to room temperature) conditions were examined for a constant total hot testing time of 80 min. The Mo matrix appears robust in a Mo-YSZ cermet and exhibits acceptable mass loss (< 1 wt%) with a sublinear dependence on exposure time (1/3 - 1/2 power) based on hydrogen testing at 2500–2630 K with thermal cycling. Moderately higher mass losses were observed for thermally cycled (4 times) vs. isothermal specimens. The subsurface Mo-YSZ interface also remains intact despite indications of debonding at the surface. Significant hydrogen attack occurs on the YSZ grain boundaries in the interior of the samples at 2500–2630 K.

Disciplines
Materials Science and Engineering
Nuclear Engineering
Degree
Doctor of Philosophy
Major
Nuclear Engineering
File(s)
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Mo_Cermet_Thesis_2.pdf

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87.96 MB

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Adobe PDF

Checksum (MD5)

5c910a21429e554e3d852def8e7e38b4

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