Effects of chromium concentration on the uniform corrosion behavior of FeCrAl alloy in hydrogenated water

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-08-14 DOI:10.1016/j.jnucmat.2025.156113

Tenghong Lin , Zhaolin Shi , Hui Wang , Donghai Du

{"title":"Effects of chromium concentration on the uniform corrosion behavior of FeCrAl alloy in hydrogenated water","authors":"Tenghong Lin , Zhaolin Shi , Hui Wang , Donghai Du","doi":"10.1016/j.jnucmat.2025.156113","DOIUrl":null,"url":null,"abstract":"<div><div>FeCrAl alloys are promising accident-tolerant fuel cladding candidates for light water reactors, where balancing irradiation and corrosion resistance is crucial. While lower Cr content generally enhances irradiation hardening resistance, its impact on high-temperature water corrosion remains unclear. Here, we systematically evaluated how Cr concentration (7–13 wt%) affects the uniform corrosion behavior of FeCrAl in simulated PWR environments. The experimental results showed that the metal loss due to corrosion reduces linearly with an increase in Cr concentration. Although 13 wt% Cr yields superior corrosion resistance, reducing Cr content to 7 wt% retains adequate corrosion resistance and demonstrates remarkable long-term stability, as evidenced by oxidation kinetics and nanoscale oxide characterization. These findings reveal that Cr reduction, potentially beneficial for irradiation resistance, does not significantly compromise corrosion performance, enabling cost-effective yet durable cladding designs.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156113"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525005070","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}

引用次数: 0

Abstract

FeCrAl alloys are promising accident-tolerant fuel cladding candidates for light water reactors, where balancing irradiation and corrosion resistance is crucial. While lower Cr content generally enhances irradiation hardening resistance, its impact on high-temperature water corrosion remains unclear. Here, we systematically evaluated how Cr concentration (7–13 wt%) affects the uniform corrosion behavior of FeCrAl in simulated PWR environments. The experimental results showed that the metal loss due to corrosion reduces linearly with an increase in Cr concentration. Although 13 wt% Cr yields superior corrosion resistance, reducing Cr content to 7 wt% retains adequate corrosion resistance and demonstrates remarkable long-term stability, as evidenced by oxidation kinetics and nanoscale oxide characterization. These findings reveal that Cr reduction, potentially beneficial for irradiation resistance, does not significantly compromise corrosion performance, enabling cost-effective yet durable cladding designs.

查看原文本刊更多论文

铬浓度对FeCrAl合金在氢化水中均匀腐蚀行为的影响

FeCrAl合金是轻水反应堆中很有前途的耐事故燃料包壳候选材料，在轻水反应堆中，平衡辐照和耐腐蚀性至关重要。虽然较低的Cr含量通常增强了抗辐照硬化性，但其对高温水腐蚀的影响尚不清楚。在这里，我们系统地评估了Cr浓度（7 - 13wt %）如何影响模拟压水堆环境中FeCrAl的均匀腐蚀行为。实验结果表明，随着Cr浓度的增加，金属的腐蚀损失呈线性降低。虽然13wt %的Cr具有优异的耐腐蚀性，但将Cr含量降低至7wt %仍能保持足够的耐腐蚀性，并表现出显著的长期稳定性，氧化动力学和纳米级氧化物表征证明了这一点。这些研究结果表明，Cr的减少对耐辐照性能有潜在的好处，但不会显著影响腐蚀性能，从而实现经济高效且耐用的包层设计。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.