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Corrosion behavior of Hastelloy-N alloys in molten salt fluoride in Ar gas or in air
Authors:Ken-ichi Fukumoto  Ryota Fujimura  Michio Yamawaki  Yuji Arita
Affiliation:1. Research Institute of Nuclear Engineering, University of Fukui, Tsuruga 914-0055, Japanfukumoto@u-fukui.ac.jp;3. Graduate School of Nuclear Power and Energy Safety Engineering, University of Fukui, Tsuruga 914-0055, Japan;4. Research Institute of Nuclear Engineering, University of Fukui, Tsuruga 914-0055, Japan
Abstract:The effects of air on the corrosion of Hastelloy-N alloys in molten salt coolant containing fission product elements were investigated to determine the safety of structural materials in high-temperature reactors cooled with fluoride salt. Corrosion tests of Hastelloy-N in the molten fluoride salt FLiNaK in an alumina crucible and a graphite crucible under argon gas or air were performed at 773–923 K for 100 h. The depth of corrosive attack, as well as the extent of chromium and molybdenum depletion, increased with increasing temperature. The extent of Hastelloy-N corrosion in molten salt under air was significantly greater than under argon gas. The effect of adding the impurity cesium iodide to molten salt containing nuclear waste fuel on the corrosion behavior was negligible.
Keywords:molten fluoride salt  corrosion  Hastelloy-N  fluoride salt-cooled high temperature reactors
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