Evaluation of Damage Tolerance of Advanced SiC/SiC Composites after Neutron Irradiation
Evaluation of Damage Tolerance of Advanced SiC/SiC Composites after Neutron Irradiation
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先进SiC/SiC复合材料中子辐照后损伤容限评价
DOI：
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发表时间：
2011
期刊：
影响因子：
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通讯作者：
L. Snead
中科院分区：
文献类型：
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作者：
K. Ozawa;Y. Katoh;T. Nozawa;T. Hinoki;L. Snead
碳化硅复合材料（SiC/SiC）是聚变能系统中结构和功能部件的理想材料。通过小型单边缺口梁试验评价了中子辐照对核级SiC/SiC复合材料（平纹编织Hi-Nicalon™ Type-S增强CVI基体复合材料多层界面和单向Tyranno™-SA 3增强NITE基体与碳单层界面）损伤容限的影响。在800°C下以5.9 × 1025 n/m2（E > 0.1 MeV）辐照和在1300° C下以5.8 × 1025 n/m2辐照后，未观察到裂纹扩展行为和载荷-载荷点位移特性（如峰值载荷和滞后回线宽度）的显著变化。通过应用基于非线性断裂力学的全局能量平衡分析，发现这些复合材料的能量释放率不受值为3±2 kJ/m2的辐照的影响。这导致的结论是，对于这些相当积极的辐照条件下，中子辐照对这些复合材料的抗断裂性的影响似乎微不足道。
Silicon carbide composites (SiC/SiC) are attractive candidate materials for structural and functional components in fusion energy systems. The effect of neutron irradiation on damage tolerance of the nuclear grade SiC/SiC composites (plain woven Hi-Nicalon™ Type-S reinforced CVI matrix composites multilayer interphase and unidirectional Tyranno™-SA3 reinforced NITE matrix with carbon mono-layer interphase) was evaluated by means of miniaturized single-edged notched beam test. No significant changes in crack extension behavior and in the load-loadpoint displacement characteristics such as the peak load and hysteresis loop width were observed after irradiation to 5.9 × 1025 n/m2 (E > 0.1 MeV) at 800°C and to 5.8 × 1025 n/m2 at 1300°C. By applying a global energy balance analysis based on non-linear fracture mechanics, the energy release rate for these composite materials was found to be unchanged by irradiation with a value of 3±2 kJ/m2. This has led to the conclusion that, for these fairly aggressive irradiation conditions, the effect of neutron irradiation on the fracture resistance of these composites appears insignificant.