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Compatibility of materials for fusion reactors with Pb–17Li
Tungsten and SiC f/SiC composite are materials considered for fusion reactors. It is therefore required to assess the corrosion behavior of these materials in contact with Pb–17Li. Corrosion tests of tungsten and SiC f/SiC composites in the presence of isothermal stagnant liquid Pb–17Li have been pe...
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Published in: | Journal of nuclear materials 2002-12, Vol.307, p.1351-1354 |
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Main Authors: | , , |
Format: | Article |
Language: | English |
Citations: | Items that this one cites Items that cite this one |
Online Access: | Get full text |
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Summary: | Tungsten and SiC
f/SiC composite are materials considered for fusion reactors. It is therefore required to assess the corrosion behavior of these materials in contact with Pb–17Li. Corrosion tests of tungsten and SiC
f/SiC composites in the presence of isothermal stagnant liquid Pb–17Li have been performed. Under the tested conditions, in the 450–800 °C temperature range, the dissolution of tungsten is very limited. Furthermore, no formation of reaction products and no liquid metal penetration have been observed. As far as the SiC
f/SiC composite is concerned, no reaction with the liquid has been observed at 800 °C. A Pb–17Li penetration has been detected in the open porosity of the cut material. |
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ISSN: | 0022-3115 1873-4820 |
DOI: | 10.1016/S0022-3115(02)00987-X |