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Recent research progress on the compatibility of tritium breeders with structural materials and coatings in fusion reactors

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Abstract

Nuclear fusion energy is considered as a clean and safe energy source. As the fuel of deuterium–tritium (D–T) fusion reactor, T must be produced by the reaction between neutron and lithium (Li) in the breeders. The blanket of fusion reactor will work in a high-temperature and radioactive environment. The long-term contact between T breeders and structural materials in such a harsh environment will result in corrosion and microstructure modification of material surfaces, and then affect the mechanical properties and thermal conductivity of materials. To protect the structural materials from corrosion, coatings are applied to their surface. In addition, the coating also plays a role in preventing T permeation. The compatibility of T breeder materials with structural materials and coatings in the breeding blanket has always been a concern. In this paper, the up-to-date data on liquid and solid blanket of fusion reactors, the interaction behavior of T breeders with candidate structural materials, including reduced activation ferritic/martensitic steel, oxide dispersion-strengthened steel, silicon carbide and vanadium alloy, and coatings are reviewed. The corrosion mechanism is also expounded. Furthermore, the corrosion behavior between different types of materials is compared comprehensively. At the end, the research and development prospects on this topic are suggested.

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Acknowledgements

This study was financially supported by the Youth Innovation Promotion Association of Chinese Academy of Sciences (2018484).

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  1. Hefei Institute of Physical Science, Chinese Academy of Sciences, Hefei, 230031, China

    Chi Wang, Bao-Long Ji, Shou-Xi Gu, Qiang Qi, Lei Chen, Hai-Shan Zhou, Song-Lin Liu & Guang-Nan Luo

  2. University of Science and Technology of China, Hefei, 230026, China

    Chi Wang, Bao-Long Ji, Shou-Xi Gu, Hai-Shan Zhou, Song-Lin Liu & Guang-Nan Luo

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  1. Chi Wang
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Wang, C., Ji, BL., Gu, SX. et al. Recent research progress on the compatibility of tritium breeders with structural materials and coatings in fusion reactors. Tungsten 4, 170–183 (2022). https://doi.org/10.1007/s42864-022-00160-7

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