4.7 Article

Corrosion and microstructural characterization of molybdenum cermets following hydrogen exposure up to 2630K

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 586, Issue -, Pages -

Publisher

ELSEVIER
DOI: 10.1016/j.jnucmat.2023.154692

Keywords

Nuclear thermal propulsion; Cermet fuels; Molybdenum Yttria-stabilized zirconia; High temperature hydrogen; Corrosion

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Ceramic-metallic (cermet) fuels show promise for space nuclear thermal propulsion systems. This study examines the hydrogen compatibility of molybdenum matrix cermets with yttria stabilized zirconia (YSZ) particles at extreme temperatures. The results show that the cermet exhibits acceptable mass loss and remains stable under high temperature hydrogen exposure.
Ceramic-metallic (cermet) fuels are a promising fuel type for space nuclear thermal propulsion (NTP). A key feasibility issue of NTP fuels 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 high temperature exposure duration of 80 min. Following testing, 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 - <1/4> 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 particle grain boundaries in the interior of the samples at 2500-2630 K.

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