Assessing Li accommodation at amorphous ZrO2 grain boundaries

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Assessing Li accommodation at amorphous ZrO2 grain boundaries. / Stephens, Gareth Frank; London, Imperial; Ghardi, Mehdi et al.
Yn: Journal of Nuclear Materials, 01.01.2024.

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Stephens GF, London I, Ghardi M, Fraile A, Rushton M, Lee B et al. Assessing Li accommodation at amorphous ZrO2 grain boundaries. Journal of Nuclear Materials. 2024 Ion 1;154780. Epub 2023 Hyd 13. doi: 10.1016/j.jnucmat.2023.154780

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Stephens, Gareth Frank ; London, Imperial ; Ghardi, Mehdi et al. / Assessing Li accommodation at amorphous ZrO2 grain boundaries. Yn: Journal of Nuclear Materials. 2024.

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TY - JOUR

T1 - Assessing Li accommodation at amorphous ZrO2 grain boundaries

AU - Stephens, Gareth Frank

AU - London, Imperial

AU - Ghardi, Mehdi

AU - Fraile, Alberto

AU - Rushton, Michael

AU - Lee, Bill

AU - Cole-Baker, Aidan

AU - Middleburgh, Simon

PY - 2024/1/1

Y1 - 2024/1/1

N2 - Nuclear Pressurised Water Reactors (PWRs) use zirconium alloys as a fuel cladding, preventing the cooling water, at elevated pH using lithium hydroxide, from interacting with the fuel. Boron, as boric acid, is added to the coolant as a reactivity shim. Future reactor designs are considering removing soluble boron reactivity control to aid plant simplification. The presence of lithium in the absence of boron in the coolant has, however, been found to accelerate the corrosion of zirconium-based alloys under certain conditions and the mechanisms by which this occurs is under investigation. The ingress of lithium into the bulk oxide layer of zirconium alloy has been addressed in a previous study and was found to be unlikely. Here, atomistic simulations were used to produce Brouwer diagrams from which the solubility of lithium in amorphous structures representing complex grain boundaries have been predicted. The solubility of lithium in these amorphous structures is predicted to be high and will produce an elevated concentration of oxygen defects within the amorphous structure. This could offer a mode for transport of oxygen to the metal oxide interface and, potentially, offer a mechanism or part of a mechanism for observed lithium-accelerated corrosion of Zr-based alloys.

AB - Nuclear Pressurised Water Reactors (PWRs) use zirconium alloys as a fuel cladding, preventing the cooling water, at elevated pH using lithium hydroxide, from interacting with the fuel. Boron, as boric acid, is added to the coolant as a reactivity shim. Future reactor designs are considering removing soluble boron reactivity control to aid plant simplification. The presence of lithium in the absence of boron in the coolant has, however, been found to accelerate the corrosion of zirconium-based alloys under certain conditions and the mechanisms by which this occurs is under investigation. The ingress of lithium into the bulk oxide layer of zirconium alloy has been addressed in a previous study and was found to be unlikely. Here, atomistic simulations were used to produce Brouwer diagrams from which the solubility of lithium in amorphous structures representing complex grain boundaries have been predicted. The solubility of lithium in these amorphous structures is predicted to be high and will produce an elevated concentration of oxygen defects within the amorphous structure. This could offer a mode for transport of oxygen to the metal oxide interface and, potentially, offer a mechanism or part of a mechanism for observed lithium-accelerated corrosion of Zr-based alloys.

U2 - 10.1016/j.jnucmat.2023.154780

DO - 10.1016/j.jnucmat.2023.154780

M3 - Article

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

M1 - 154780

ER -