首页|Chemical interactions between ZrO2/alpha-Zr structured Zircaloy-4 and 316 stainless steel-B4C melt at 1300 degrees C
Chemical interactions between ZrO2/alpha-Zr structured Zircaloy-4 and 316 stainless steel-B4C melt at 1300 degrees C
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NSTL
Elsevier
To deeply understand chemical interactions among nuclear materials during core meltdown, pre-oxidized Zircaloy-4 was re-heated under oxygen starvation to form thermodynamically stable ZrO2/alpha-Zr structure and then brought into contact with 316SS-B4C melt at 1300 degrees C. During re-heating, initial ZrO2 layer was partially dissolved due to thermodynamic instability, forming a new alpha-Zr layer at the external surface. Dissolution of ZrO2 layer could be linearly fitted with fourth root of re-heating time. When pre-oxidized and then re-heated Zircaloy-4 contacted with 316SS-B4C melt, the external alpha-Zr layer became oxygen-unsaturated and was dissolved first by 316SS-B4C melt. Initial ZrO2 layer was divided into two sublayers from the position where Zr5Sn3 phase was located. Due to direct contact with oxygen-unsaturated alpha-Zr layer, outer ZrO2 sublayer became thermodynamically unstable and was dissolved more rapidly than inner sublayer. The reaction zone consisting of multiple sublayers grew approximately linearly with time. Consequently, pre-oxidized and then re-heated Zircaloy-4 showed no significant improvement in delaying ZrO2 dissolution and reaction zone formation under the current experimental conditions, compared with only pre-oxidized Zircaloy-4. (C) 2021 Elsevier B.V. All rights reserved.
NSTL
Elsevier
