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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >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
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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

机译：循环热冲击后碳化硅，氧化锆和铝酸铝基惰性基质核燃料材料的力学性能和导热系数的研究

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Modification of thermo-mechanical properties of simulated (SiC) silicon carbide-, (ZrO2) zirconia- and (MgAl2O4) spinel-based inert matrix nuclear fuels after cyclic thermal shock was analyzed in terms of Vickers hardness (H-V), fracture toughness (K-IC) and thermal conductivity. Three different simulated specimens were used for the experiment; a solid solution of yttria-stabilized zirconia and ceria (composition: Er0.07Y0.10Ce0.15Zr0.68O1.915, 92.0% TD, specimen hereafter called Ce-ZrO2), a CeO2-dispersed Mg-spinel (composition: 15wt%CeO2-MgAl2O4, 93.7% TD, specimen hereafter called Ce-spinel) and a CeO2-dispersed silicon carbide (composition: 80.8 wt% SiC, 6.9 wt% Al2O3, 5.1 wt% Y2O3 and 5.0 wt% CeO2, specimen hereafter called Ce-SiC), CeO2 being surrogate materials for PuO2 Cyclic thermal shock experiment and thermal conductivity measurements were simultaneously carried out by heating disc-shaped specimens up to maximum temperature ranging from 1073 to 1673 K and then cooling down to 343 K with Ar gas during 20-25 min. The Vickers hardness of the three different thermally shocked specimens showed nearly constant values with increasing number of cycles, except for the specimen heated at 1673 K. The K-IC values of the corresponding specimens increased with the increasing number of cyclic thermal shock at 1673 K. For Ce-ZrO2 heated at 1673 K, however, it decreases considerably due to the combined effects of formation of second phase and modification of the matrix composition thereby. The calculated thermal conductivity of Ce-spinel decreases as the number of cycles in thermal shock increases in the temperature range between 1073 and 1673 K, and Ce-SiC slightly decreased with the number of cycles in cyclic thermal shock and the variations in thermal conductivity are almost the same for the temperature increases of 1073 and 1373 K, whereas, in Ce-ZrO2, it remains nearly constant. (C) 2003 Elsevier Science B.V. All rights reserved. [References: 12]
机译：根据维氏硬度（HV），断裂韧性（K）对循环热冲击后模拟（SiC）碳化硅，（ZrO2）氧化锆和（MgAl2O4）尖晶石型惰性基质核燃料的热机械性能进行了分析-IC）和热导率。实验使用了三个不同的模拟标本。氧化钇稳定的氧化锆和二氧化铈的固溶体（成分：Er0.07Y0.10Ce0.15Zr0.68O1.915，92.0％TD，以下称为Ce-ZrO2），CeO2分散的Mg-尖晶石（成分：15wt％CeO2 -MgAl 2 O 4，TD为93.7％，以下称为Ce-spinel样品;和CeO 2分散的碳化硅（成分：80.8wt％的SiC，6.9wt％的Al 2 O 3，5.1wt％的Y 2 O 3和5.0wt％的CeO 2，以下称为Ce-SiC ），CeO2是PuO2的替代材料循环热冲击实验和热导率测量是通过将圆盘形试样加热到最高温度范围从1073至1673 K，然后在20-25℃下用Ar气冷却至343 K来同时进行的分钟三种不同的热冲击试样的维氏硬度随循环次数的增加显示出几乎恒定的值，除了加热到1673 K的试样外。相应的试样的K-IC值随着1673 K的循环热冲击次数的增加而增加。然而，对于在1673 K下加热的Ce-ZrO2，由于第二相的形成和基体组成的改变的综合作用，其显着降低。 Ce-尖晶石的热导率在1073和1673 K之间的温度范围内随着热冲击循环数的增加而降低，而Ce-SiC随着循环热冲击循环数的增加而略有下降，并且热导率的变化为温度升高1073和1373 K时几乎相同，而在Ce-ZrO2中则几乎保持恒定。 （C）2003 Elsevier Science B.V.保留所有权利。 [参考：12]

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