TY - JOUR
T1 - Elemental gradient potential trap strategy for enhancing corrosion resistance of SiC in oxygenated and oxygen-free lead-bismuth corrosion
AU - Hui, Jun
AU - Chen, Jiapeng
AU - Liu, Min
AU - Wang, Shuo
AU - Wang, Biao
N1 - Publisher Copyright:
© 2025 Elsevier B.V.
PY - 2025/11
Y1 - 2025/11
N2 - SiC is a promising candidate for producing corrosion-resistant lead–bismuth cladding material for application in lead-cooled fast reactors because of its excellent properties, including high resistance to oxidation and thermal shock, high thermal conductivity, and low thermal expansion in flowing lead–bismuth material. The present study revealed the following. First, the binding behavior of Pb/Bi material on its free surface is mainly influenced by the shell energy; in the bulk, the core energy plays a larger role. Second, at the free surface of SiC, Si atoms partially lose their coordination and accumulate an electron energy of approximately 1.3 eV, leading to a 0.74 % decrease in the length of the Si–C bond, which enhances the local binding strength. By contrast, exposure of the C layer results in a loss of approximately 0.5 eV in the electron energy, which causes a 4.81 % contraction of the length of the Si–C bond. The charge depletion in the Si layer and bond contraction in the C layer contribute synergistically to corrosion resistance. Third, a gradient effect exists between the free surface and the bulk; surface elements tend to repel Pb/Bi, whereas bulk elements can either attract or repel Pb/Bi. Gradient doping at the free surface and in the bulk regions reduces Pb/Bi adsorption on the surface and modulates the Pb/Bi binding energy in the bulk, improving the overall corrosion resistance of SiC. This study provides essential theoretical support for the application of SiC as a cladding material in generation IV lead-cooled fast reactors. The proposed elemental gradient potential trapping (EGPT) strategy enhances the corrosion and irradiation resistance of SiC, thereby improving its overall performance in high-temperature environments where both irradiation and corrosion occur.
AB - SiC is a promising candidate for producing corrosion-resistant lead–bismuth cladding material for application in lead-cooled fast reactors because of its excellent properties, including high resistance to oxidation and thermal shock, high thermal conductivity, and low thermal expansion in flowing lead–bismuth material. The present study revealed the following. First, the binding behavior of Pb/Bi material on its free surface is mainly influenced by the shell energy; in the bulk, the core energy plays a larger role. Second, at the free surface of SiC, Si atoms partially lose their coordination and accumulate an electron energy of approximately 1.3 eV, leading to a 0.74 % decrease in the length of the Si–C bond, which enhances the local binding strength. By contrast, exposure of the C layer results in a loss of approximately 0.5 eV in the electron energy, which causes a 4.81 % contraction of the length of the Si–C bond. The charge depletion in the Si layer and bond contraction in the C layer contribute synergistically to corrosion resistance. Third, a gradient effect exists between the free surface and the bulk; surface elements tend to repel Pb/Bi, whereas bulk elements can either attract or repel Pb/Bi. Gradient doping at the free surface and in the bulk regions reduces Pb/Bi adsorption on the surface and modulates the Pb/Bi binding energy in the bulk, improving the overall corrosion resistance of SiC. This study provides essential theoretical support for the application of SiC as a cladding material in generation IV lead-cooled fast reactors. The proposed elemental gradient potential trapping (EGPT) strategy enhances the corrosion and irradiation resistance of SiC, thereby improving its overall performance in high-temperature environments where both irradiation and corrosion occur.
KW - Lead–bismuth corrosion
KW - Oxygen adsorption
KW - SiC
UR - https://www.scopus.com/pages/publications/105015767894
U2 - 10.1016/j.jnucmat.2025.156160
DO - 10.1016/j.jnucmat.2025.156160
M3 - Article
AN - SCOPUS:105015767894
SN - 0022-3115
VL - 617
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 156160
ER -