EPJ Nuclear Sci. Technol.
Volume 6, 2020
Progress in the Science and Technology of Nuclear Reactors using Molten Salts
|Number of page(s)||12|
|Published online||20 January 2020|
Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF2-UF4 salt
National Research Centre “Kurchatov Institute” (NRC KI), Kurchatov sq., 1, 123182 Moscow, Russia
2 Shanghai Institute of Applied Physics (SINAP), Chinese Academy of Sciences, 201800 Shanghai, Jiading, P.R. China
* e-mail: firstname.lastname@example.org
Received in final form: 13 September 2019
Accepted: 27 September 2019
Published online: 20 January 2020
Effect of the [U(IV)/U(III)] ratio of fuel salt on selective chromium corrosion and tellurium intergranular cracking (IGC) of Hastelloy N alloy in the LiF-BeF2-UF4 salt mixture was investigated. The chromium corrosion of Hastelloy N alloy is caused by the oxidation of chromium on the alloy surface by reaction with UF4. The tellurium IGC of Hastelloy N alloy is caused by the diffusion of tellurium along the grain boundaries with the formation of unstable tellurides with based metals and alloying additives. Results indicate that the selective chromium corrosion and the tellurium IGC of the Hastelloy N alloy in fuel salt can be controlled by the [U(IV)]/[U(III)] ratio. The tellurium IGC of Hastelloy N alloy exposed in fuel LiF-BeF2-UF4 salt can be avoided. For temperatures up to 760 °C the selective chromium corrosion can be minimized to the acceptable level when the [U(IV)]/[U(III)] ratio of fuel salt is bellow 30–40.
© A. Surenkov et al., published by EDP Sciences, 2020
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