Santiago Bermudez , Furkan Erdogan , Victoria Davis , Jessika V. Rojas , Rajnikant V. Umretiya
{"title":"Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000 °C)","authors":"Santiago Bermudez , Furkan Erdogan , Victoria Davis , Jessika V. Rojas , Rajnikant V. Umretiya","doi":"10.1016/j.nme.2025.101972","DOIUrl":null,"url":null,"abstract":"<div><div>Despite their widespread application, FeCrAl alloys face several challenges in maintaining performance under high thermal cycling and extreme oxidation conditions. Following the 2011 Fukushima Daiichi accident, there has been a growing interest on developing of accident tolerant fuel (ATF) cladding materials, as well as modifications to existing ones, for advanced nuclear reactors. This study investigates the role of nickel in enhancing the high-temperature oxidation resistance of FeCrAl alloys, which are being considered as potential replacements for zirconium alloys. Specifically, the oxidation behavior of FeCrAl alloys with 17 wt% chromium and varying nickel contents Fe-17Cr-5.5Al, Fe-17Cr-5.5Al-1Ni, and Fe-17Cr-5.5Al-3Ni were examined under steam environment at 1000 °C for 5000 s. The oxide layer thickness and compositional changes were characterized using X-ray diffraction (XRD), scanning electron microscopy (SEM-EDX) and transmission electron microscopy (TEM). The results indicate that low nickel concentrations significantly improve the oxidation resistance of FeCrAl alloys, making them more suitable for accident-tolerant fuel cladding applications in advanced nuclear reactors. This study provides valuable insights in optimizing FeCrAl alloy compositions to improve their oxidation resistance under extreme conditions.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101972"},"PeriodicalIF":2.7000,"publicationDate":"2025-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S2352179125001140","RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Despite their widespread application, FeCrAl alloys face several challenges in maintaining performance under high thermal cycling and extreme oxidation conditions. Following the 2011 Fukushima Daiichi accident, there has been a growing interest on developing of accident tolerant fuel (ATF) cladding materials, as well as modifications to existing ones, for advanced nuclear reactors. This study investigates the role of nickel in enhancing the high-temperature oxidation resistance of FeCrAl alloys, which are being considered as potential replacements for zirconium alloys. Specifically, the oxidation behavior of FeCrAl alloys with 17 wt% chromium and varying nickel contents Fe-17Cr-5.5Al, Fe-17Cr-5.5Al-1Ni, and Fe-17Cr-5.5Al-3Ni were examined under steam environment at 1000 °C for 5000 s. The oxide layer thickness and compositional changes were characterized using X-ray diffraction (XRD), scanning electron microscopy (SEM-EDX) and transmission electron microscopy (TEM). The results indicate that low nickel concentrations significantly improve the oxidation resistance of FeCrAl alloys, making them more suitable for accident-tolerant fuel cladding applications in advanced nuclear reactors. This study provides valuable insights in optimizing FeCrAl alloy compositions to improve their oxidation resistance under extreme conditions.
期刊介绍:
The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.