Abstract
One proposed blanket concept uses advanced ferritic alloys and a SiC/SiC composite flow channel insert with both Pb-17 at.%Li and He coolants. As the first step in determining the long-term compatibility of SiC/SiC in Pb-Li, specimens of high-purity, chemical vapor deposited (CVD) SiC were exposed in capsules for up to 5000 h at 800 °C and 1000 h at 1200 °C. Dissolved Si was detected in the Pb-Li after the highest temperature exposures suggesting that SiC may be limited to <1100 °C in Pb-Li. Aluminide coatings are being considered for corrosion resistant coatings for the tubing between the first wall and the heat exchanger. Initial results indicate that, in Pb-Li at 700 °C, FeCrAl, Fe3Al and NiAl form a protective alumina layer which reduces dissolution compared to type 316 stainless steel.
Cite
CITATION STYLE
Pint, B. A., Moser, J. L., & Tortorelli, P. F. (2007). Investigation of Pb-Li compatibility issues for the dual coolant blanket concept. Journal of Nuclear Materials, 367-370 B(SPEC. ISS.), 1150–1154. https://doi.org/10.1016/j.jnucmat.2007.03.206
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