Characterization of Yttria-Stabilized Zirconia (YSZ) following high temperature hydrogen exposures of molybdenum-YSZ composites

被引：2
|
作者：
Duffin, Taylor G. [1 ]
Palomares, Kelsa B. [2 ]
Zinkle, Steven J. [1 ]
机构：
[1] Univ Tennessee, Nucl Engn, Knoxville, TN 37996 USA
[2] Analyt Mech Associates, Huntsville, AL USA
来源：
JOURNAL OF NUCLEAR MATERIALS | 2024年 / 591卷
关键词：
Nuclear thermal propulsion; Cermet fuels; Yttria-stabilized zirconia; High temperature hydrogen; Corrosion; THERMAL-EXPANSION; DIFFUSION; REDUCTION; OXIDES; PARAMETERS; SOLUBILITY; FUEL;
D O I：
10.1016/j.jnucmat.2023.154894
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Molybdenum matrix ceramic-metal (cermet) composites 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. Due to the high hydrogen permeability in Mo at these temperatures, pronounced microstructural degradation was observed in YSZ particles located many millimeters below the sample surface. Observed changes to the YSZ particles from the hot hydrogen testing include partial matrix debonding, thermal expansion, redeposition of material, phase changes to a monoclinic phase and cracking/bubble formation on the YSZ grain boundaries. Overall, the YSZ particles exhibited acceptable tolerance to this extreme operating environment.
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页数：11
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