High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application
The corrosion of nuclear-grade steels in lead–bismuth eutectic (LBE) complicates the realization of high coolant temperatures. Corrosion tests of T91, HT9, and SS316L were performed in static cells at 600 °C for 2000 h at an oxygen level of 10<sup>–6</sup> wt.%. The obtained corrosion su...
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doaj-b8c7b7d992964cd2aa3b86db952434b32021-03-07T00:02:39ZengMDPI AGApplied Sciences2076-34172021-03-01112349234910.3390/app11052349High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor ApplicationSeung Gi Lee0Yong-Hoon Shin1Jaeyeong Park2Il Soon Hwang3Department of Energy Systems Engineering, Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826, KoreaDepartment of Energy Systems Engineering, Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826, KoreaDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, Ulju-gun, Ulsan 44919, KoreaDepartment of Energy Systems Engineering, Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826, KoreaThe corrosion of nuclear-grade steels in lead–bismuth eutectic (LBE) complicates the realization of high coolant temperatures. Corrosion tests of T91, HT9, and SS316L were performed in static cells at 600 °C for 2000 h at an oxygen level of 10<sup>–6</sup> wt.%. The obtained corrosion surfaces of post-processed samples were characterized by several microscopy methods. Up to 1000 h, all the alloys exhibited an evolution of duplex oxide layers, which were spalled until 2000 h due to their increased thickness and decreased integrity. Following the spallation, a thin internal Cr-rich oxide layer was formed above the Cr-depleted zone for T91 and HT9. SS316L was penetrated by LBE down to 300 μm in severe cases. A comparison on the corrosion depths of the materials with regard to the parabolic oxidation law with abundant literature data suggests that it may lose its validity once the duplex layer is destroyed as it allows LBE to penetrate the metal substrate.https://www.mdpi.com/2076-3417/11/5/2349LBElead-alloy-cooled fast reactorhigh-temperature corrosionstainless steelHT9T91 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Seung Gi Lee Yong-Hoon Shin Jaeyeong Park Il Soon Hwang |
spellingShingle |
Seung Gi Lee Yong-Hoon Shin Jaeyeong Park Il Soon Hwang High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application Applied Sciences LBE lead-alloy-cooled fast reactor high-temperature corrosion stainless steel HT9 T91 |
author_facet |
Seung Gi Lee Yong-Hoon Shin Jaeyeong Park Il Soon Hwang |
author_sort |
Seung Gi Lee |
title |
High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application |
title_short |
High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application |
title_full |
High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application |
title_fullStr |
High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application |
title_full_unstemmed |
High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application |
title_sort |
high-temperature corrosion behaviors of structural materials for lead-alloy-cooled fast reactor application |
publisher |
MDPI AG |
series |
Applied Sciences |
issn |
2076-3417 |
publishDate |
2021-03-01 |
description |
The corrosion of nuclear-grade steels in lead–bismuth eutectic (LBE) complicates the realization of high coolant temperatures. Corrosion tests of T91, HT9, and SS316L were performed in static cells at 600 °C for 2000 h at an oxygen level of 10<sup>–6</sup> wt.%. The obtained corrosion surfaces of post-processed samples were characterized by several microscopy methods. Up to 1000 h, all the alloys exhibited an evolution of duplex oxide layers, which were spalled until 2000 h due to their increased thickness and decreased integrity. Following the spallation, a thin internal Cr-rich oxide layer was formed above the Cr-depleted zone for T91 and HT9. SS316L was penetrated by LBE down to 300 μm in severe cases. A comparison on the corrosion depths of the materials with regard to the parabolic oxidation law with abundant literature data suggests that it may lose its validity once the duplex layer is destroyed as it allows LBE to penetrate the metal substrate. |
topic |
LBE lead-alloy-cooled fast reactor high-temperature corrosion stainless steel HT9 T91 |
url |
https://www.mdpi.com/2076-3417/11/5/2349 |
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