Abstract
This paper reports on the microstructure and properties of two glass–ceramics based on SiO2–Al2O3–MgO (SAMg) and SiO2–Al2O3–Y2O3 (SAY), which have been designed to be used as pressure-less low activation joining materials for SiC/SiC and SiC based components for nuclear applications. Glass–ceramic pellets (SAY and SAMg) were irradiated for approximately 1year in the reactor core of the LVR-15 research reactor at Nuclear Research Institute Rez, Czech Republic, at about 50°C, 6.92×1024n/m2 (E>1MeV, about 1dpa in steel); SiC/SiC composites joined by SAY were irradiated about 1year at High Flux Reactor (HFR), Petten, The Netherlands, 550°C, 9–11×1024n/m2 (E>1MeV, about 1.4–1.8dpa in C), 600°C, 16–22×1024n/m2 (E>1MeV, about 2.6–3.3dpa in C) and 820°C 31–32×1024n/m2(E>1MeV, about 5dpa in C). Optical microscopy with image analysis and scanning electron microscopy (SEM) with X-ray microanalysis (EDS) were used to investigate the glass–ceramics morphology and composition, showing a remarkable similarity before and after neutron irradiation for both glass–ceramics. Comparison of bending strength for irradiated and non-irradiated SAY joined SiC/SiC indicate that the mechanical strength is unaffected by irradiation at these conditions.
Published Version
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