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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Main Authors: Seung Gi Lee, Yong-Hoon Shin, Jaeyeong Park, Il Soon Hwang
Format: Article
Language:English
Published: MDPI AG 2021-03-01
Series:Applied Sciences
Subjects:
LBE
HT9
T91
Online Access:https://www.mdpi.com/2076-3417/11/5/2349
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spelling 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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