Study on the mechanical properties and thermal conductivity of silicon carbide-, zirconia- and magnesia aluminate-based simulated inert matrix nuclear fuel materials after cyclic thermal shock

Evaluation of thermal conductivity of zirconia-based inert matrix fuel by molecular dynamics simulation

“…5. This figure also includes experimental data of Er 0.07 Y 0.1 Ce 0.15 Zr 0.68 O 1.915 [2,8], which are corrected for porosity. The present EMD result shows that the thermal conductivity of Er 0.05 Y 0.1 Ce z Zr 0.85Àz O 1.925 decreases a little with increase in temperature and Ce content, z.…”

“…So far, for zirconia-based IMF, Er x Y y Pu zZr 1ÀxÀyÀz O 2À(x+y)/2 (x + y = $0.15), various physico-chemical properties have been investigated by both experimental and simulation methods [2,[4][5][6][7][8][9]. Since thermal conductivity is one of the most important parameters for a nuclear fuel, it must be carefully evaluated by different approaches.…”

Processing of uranium oxide and silicon carbide based fuel using polymer infiltration and pyrolysis

“…Therefore, there have been many efforts to develop SiC based composites in various forms for use in advanced energy systems [5,6]. Alkan et al [5] proposed a joining technique of SiC parts so that the fissile material could be encapsulated in SiC capsules.…”

“…Alkan et al [5] proposed a joining technique of SiC parts so that the fissile material could be encapsulated in SiC capsules. Lee et al [6] studied the effect of cyclic thermal shock on the mechanical and thermal properties of various ceramics being considered as candidates for nuclear fuel matrices. They observed that the silicon carbide based material exhibited superior mechanical and thermal shock performance at higher temperatures, as compared to those based on zirconia or magnesia aluminate.…”

Atomistic simulation of rapid compression of fractured silicon carbide

“…The nuclear industry foresees application of SiC in structural components like the inner wall of fusion reactors and innovative fuels [3,4]. The high thermal conductivity and melting point and favourable mechanical properties of this material combined with neutron transparency make it a promising candidate for application as inert matrix in advanced fuels for next generation gas reactor and actinide transmutation systems [5].…”