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Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors

In order to meet the growing energy demand, more environmentally friendly and efficient GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more safety margins for accident scenarios as a result of the Fukushima accident. In order to extend the failure time and lesse...

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Autores principales: Jia, Haodong, Wang, Yingjie, Wang, You, Han, Lu, Zhang, Yujuan, Zhou, Zhangjian
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2023
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC10180414/
https://www.ncbi.nlm.nih.gov/pubmed/37176379
http://dx.doi.org/10.3390/ma16093497
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author Jia, Haodong
Wang, Yingjie
Wang, You
Han, Lu
Zhang, Yujuan
Zhou, Zhangjian
author_facet Jia, Haodong
Wang, Yingjie
Wang, You
Han, Lu
Zhang, Yujuan
Zhou, Zhangjian
author_sort Jia, Haodong
collection PubMed
description In order to meet the growing energy demand, more environmentally friendly and efficient GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more safety margins for accident scenarios as a result of the Fukushima accident. In order to extend the failure time and lessen the effect of accidents, this design method for accident-tolerant fuel materials calls for cladding materials to maintain good corrosion resistance and mechanical properties during a beyond design basis accident (BDBA). Accidents involving nuclear reactors would undoubtedly result in higher temperatures, which would make it much harder for materials to withstand corrosion. Oxide dispersion strengthened (ODS) FeCrAl alloys have shown promise as candidate materials because of their extraordinarily slow reaction rates under high-temperature steam. However, the addition of the Al element renders the alloy’s high-temperature mechanical properties insufficient. In particular, studies on the alloy’s creep properties are extremely rare, despite the fact that the creep properties are crucial in the real service environment. Therefore, this paper focuses on the creep properties of ODS FeCrAl alloy, summarizes and analyzes the research results of this material, and provides a reference for future research and applications.
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spelling pubmed-101804142023-05-13 Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors Jia, Haodong Wang, Yingjie Wang, You Han, Lu Zhang, Yujuan Zhou, Zhangjian Materials (Basel) Review In order to meet the growing energy demand, more environmentally friendly and efficient GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more safety margins for accident scenarios as a result of the Fukushima accident. In order to extend the failure time and lessen the effect of accidents, this design method for accident-tolerant fuel materials calls for cladding materials to maintain good corrosion resistance and mechanical properties during a beyond design basis accident (BDBA). Accidents involving nuclear reactors would undoubtedly result in higher temperatures, which would make it much harder for materials to withstand corrosion. Oxide dispersion strengthened (ODS) FeCrAl alloys have shown promise as candidate materials because of their extraordinarily slow reaction rates under high-temperature steam. However, the addition of the Al element renders the alloy’s high-temperature mechanical properties insufficient. In particular, studies on the alloy’s creep properties are extremely rare, despite the fact that the creep properties are crucial in the real service environment. Therefore, this paper focuses on the creep properties of ODS FeCrAl alloy, summarizes and analyzes the research results of this material, and provides a reference for future research and applications. MDPI 2023-05-01 /pmc/articles/PMC10180414/ /pubmed/37176379 http://dx.doi.org/10.3390/ma16093497 Text en © 2023 by the authors. https://creativecommons.org/licenses/by/4.0/Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/).
spellingShingle Review
Jia, Haodong
Wang, Yingjie
Wang, You
Han, Lu
Zhang, Yujuan
Zhou, Zhangjian
Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
title Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
title_full Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
title_fullStr Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
title_full_unstemmed Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
title_short Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
title_sort recent progress on creep properties of ods fecral alloys for advanced reactors
topic Review
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC10180414/
https://www.ncbi.nlm.nih.gov/pubmed/37176379
http://dx.doi.org/10.3390/ma16093497
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