Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 472, Issue -, Pages 28-34Publisher
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2016.01.024
Keywords
Glass-ceramics; Radiation-induced damage; Microstructure analysis; Materials for nuclear fusion plants
Funding
- European Union Seventh Framework Programme [312483-ESTEEM2]
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CaO-Al2O3 (CA) and SiO2-Al2O3-Y2O3 (SAY) glass-ceramics are promising candidates for SiC/SiC indirect joints. In view of their use in locations where high radiation level is expected (i.e. fusion plants) it is important to investigate how radiation-induced damage can modify the material microstructure. To this aim, pellets of both types were irradiated with 5.5 MeV He-4(+) ions at an average temperature of 75 degrees C up to a fluence of almost 2.3.10(18) cm(-2). This produces a displacement defect density that increases with depth and reaches a value of about 40 displacements per atom in the ion implantation region, where the He-gas reaches a concentration of several thousands of atomic parts per million. X-ray diffractometry and scanning electron microscopy showed no change in the microstructure and in the morphology of the pellet surface. Moreover, a transmission electron microscopy investigation on cross-section lamellas revealed the occurrence of structural defects and agglomerates of He-bubbles in the implantation region for the CA sample and a more homogeneous He-bubble distribution in the SAY pellet, even outside the implantation layer. In addition, no amorphization was found in both samples, even in correspondence to the He implantation zone. The radiation damage induced only occasional micro-cracks, mainly located at grain boundaries (CA) or within the grains (SAY). (C) 2016 Elsevier B.V. All rights reserved.
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