1. Development, Characterization, and Testing of a SiC-Based Material for Flow Channel Inserts in High-Temperature DCLL Blankets.
- Author
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Soto, Carlota, Garcia-Rosales, Carmen, Echeberria, Jon, Platacis, Ernests, Shisko, Andrejs, Muktepavela, Faina, Hernandez, Teresa, and Huertac, Marta Malo
- Subjects
FUSION reactor blankets ,FUSION reactor materials ,NUCLEAR reactor materials ,SILICON carbide testing ,SILICON carbide ,NUCLEAR reactor cooling ,NUCLEAR reactor cooling equipment ,THERMAL conductivity measurement ,THERMAL properties - Abstract
Flow channel inserts (FCIs) are the key elements in the high-temperature dual-coolant lead-lithium blanket, since in this concept the flowing PbLi reaches temperatures near 700 °C and FCIs should provide the necessary thermal and electrical insulations to assure a safe blanket performance. In this paper, the use of a SiC-sandwich material for FCIs consisting of a porous SiC core covered by a dense chemical vapor deposition-SiC layer is studied. A fabrication procedure for porous SiC is proposed and the resulting materials are characterized in terms of thermal and electrical conductivities (the latter before and after being subjected to ionizing radiation) and flexural strength. SiC materials with a wide range of porosities are produced; in addition, preliminary results using an alternative route based on the gel-casting technique are also presented, including the fabrication of hollow samples to be part of future lab-scale FCI prototypes. Finally, to study the corrosion resistance of the material in hot PbLi, corrosion tests under static PbLi at 700 °C and under flowing PbLi at ~10 cm/s and 550 °C, with and without a 1.8–2T magnetic field, were performed to materials coated with a 200–400- $\mu \text{m}$ -thick dense SiC layer, obtaining promising results. [ABSTRACT FROM AUTHOR]
- Published
- 2018
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