Fabrication and volume loading studies for Mo30W matrix surrogate cermets

被引:1
|
作者
Gaffin, Neal D. [1 ]
Palomares, Kelsa B. [2 ]
Milner, Justin L. [3 ]
Zinkle, Steven J. [1 ]
机构
[1] Univ Tennessee, 863 Neyland Dr, Knoxville, TN 37996 USA
[2] Analyt Mech Associates Inc, Adv Projects Grp, Huntsville, AL 35806 USA
[3] NASA Glenn Res Ctr, 21000 Brookpark Rd, Cleveland, OH 44135 USA
关键词
Molybdenum tungsten alloy (MoW); Refractory alloys; Spark plasma sintering (SPS); High temperature refractory alloy; Ceramic metallic (cermet) composite; Nuclear thermal propulsion (NTP); YTTRIA-STABILIZED ZIRCONIA; THERMAL-CONDUCTIVITY; URANIUM NITRIDE; MECHANICAL-PROPERTIES; HIGH-TEMPERATURE; HAFNIUM NITRIDE; HEAT-CAPACITY; MOLYBDENUM; DIFFUSION; TUNGSTEN;
D O I
10.1016/j.ijrmhm.2023.106413
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Ceramic-metallic composite (cermet) fuel forms are promising options for use in nuclear thermal propulsion (NTP) due to their high melting point, inherent hydrogen compatibility, retained strength at high temperatures, and high thermal conductivity. Spark plasma sintering was used to fabricate cermet materials, resulting in improved microstructural characteristics. An alloy of molybdenum with 30 wt% tungsten was used as the matrix material. Spherical yttria stabilized zirconia (YSZ) and both spherical and angular hafnium nitride (HfN) were used as surrogate fuel particles for the cermets. Utilizing a new lab-scale particle coating method, high density composites with excellent particle-matrix interfaces were fabricated. The effects of volume loading on the microstructure of the matrix were also examined, testing particle loadings up to 90 vol%. Initial stage sintering models were applied to understand the effects of the added particles on the sintering of the Mo30W matrix. Recommendations for fabrication of uranium bearing cermets using Mo30W are also included.
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页数:14
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