Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants
EPJ Nuclear Sci. Technol., 3 (2017) 34
Published online: 2017-12-12
Articles citing this article
The Citing articles tool gives a list of articles citing the current article.
The citing articles come from EDP Sciences database, as well as other publishers participating in CrossRef Cited-by Linking Program. You can set up your personal account to receive an email alert each time this article is cited by a new article (see the menu on the right-hand side of the abstract page).
Cited article:
This article has been cited by the following article(s):
Experimental and analytical investigations to reduce MHD pressure drop for liquid LiPb fusion blanket systems: use of ODS-FeCrAl alloys with electrically insulating α-Al2O3 layer in optimal flow channel geometry
Ryunosuke Nishio, Masatoshi Kondo, Teruya Tanaka and Naoko Oono-HoriNuclear Materials and Energy 44 101965 (2025)
https://doi.org/10.1016/j.nme.2025.101965
Double-differential-cross-section measurements of neutron scattering on Fe56
G. Gkatis, M. Diakaki, G. Noguere, A. Oprea, C. Paradela, E. Pirovano and A. J. M. PlompenPhysical Review C 112 (4) (2025)
https://doi.org/10.1103/b5n2-9kxn
EFFECT OF DIFFUSE NITROGEN SATURATION ON THE STRUCTURE AND MICROHARDNESS OF THE SURFACE LAYER OF Zr-1Nb
V.S. Trush, N.N. Pylypenko, P.I. Stoev, V.M. Fedirko, M.A. Tikhonovsky, I.M. Pohrelyuk, A.G. Luk’yanenko, S.M. Lavrys, K.V. Trush, V.M. Korendiy, A.E. Stetsko, R.Ya. Predko, T.M. Kravchyshyn and Ya.Ya. SirakProblems of Atomic Science and Technology 27 (2025)
https://doi.org/10.46813/2025-156-027
Sequential oxidation and hydrothermal corrosion of FeCrAl alloys at BWR top-of-core conditions
Ronit Roy, Arya Chatterjee, Soumita Mondal, Md Ali Muntaha, Janelle P. Wharry, Haozheng J. Qu and Rajnikant UmretiyaCorrosion Science 252 112965 (2025)
https://doi.org/10.1016/j.corsci.2025.112965
Evolutionary Process of Worker Behavior Risk in Nuclear Power Plants Under Construction Based on Multi-Source Fusion Algorithm: A Case Study of BN–Game–SD
Weibo Yang, Jianzhan Gao, Yuwei Huang, Kai Yu and Zhaoxiang MuProcesses 13 (6) 1661 (2025)
https://doi.org/10.3390/pr13061661
Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water
Zihao Lin, Ziyu Zhang, Jibo Tan and Xinqiang WuJournal of Nuclear Materials 603 155454 (2025)
https://doi.org/10.1016/j.jnucmat.2024.155454
1 (2025)
https://doi.org/10.1007/978-981-96-5028-6_1
Characteristic, corrosion and high-temperature steam oxidation behavior of FeCrAl-coated Zr alloy by magnetron sputtering: Synergistic effect of deposition temperature and substrate bias
Xiaoling Yang, Baifeng Luan, Jinlong Wu, Lijun Chen, Huiyi Tang, Haibo Ruan and Weijiu HuangSurface and Coatings Technology 498 131783 (2025)
https://doi.org/10.1016/j.surfcoat.2025.131783
Effect of aging and α’ segregation on oxidation and electrochemical behavior of FeCrAl alloys
Rupesh Rajendran, Atharva S Chikhalikar, Indranil Roy, Hamdy Abouelella, Haozheng J. Qu, Rajnikant V. Umretiya, Andrew K. Hoffman and Raul B. RebakJournal of Nuclear Materials 588 154751 (2024)
https://doi.org/10.1016/j.jnucmat.2023.154751
Realistic performance assessment of FeCrAl-UN/U3Si2 accident tolerant fuel under loss-of-coolant accident scenario
Qingwen Xiong, Libo Qian, Gongle Song, Jiewei Yang, Yu Liu, Jian Deng and Zhifang QiuReliability Engineering & System Safety 243 109847 (2024)
https://doi.org/10.1016/j.ress.2023.109847
93 (2024)
https://doi.org/10.1016/B978-0-323-99880-2.00005-9
Temperature-dependent thermal conductivity and fuel performance of UN-UO2 and UN-X-UO2 (X=Mo, W) composite nuclear fuels by finite element modeling
Faris Sweidan, Diogo Ribeiro Costa, Huan Liu and Pär OlssonJournal of Materiomics 10 (4) 937 (2024)
https://doi.org/10.1016/j.jmat.2024.02.007
Study of neutronic and creep properties of Kanthal APMT for advanced fuel cladding applications
Arnold Pradhan, Triratna Shrestha, Christopher S. Starr, Thomas B. McCall and Indrajit CharitProgress in Nuclear Energy 173 105257 (2024)
https://doi.org/10.1016/j.pnucene.2024.105257
Corrosion Resistance of Traditional and Advanced Fuel Rod Cladding Materials for Water-Cooled Reactors
Progress in Physics of Metals 25 (2) (2024)https://doi.org/10.15407/ufm.25.02.243
Using MELCOR with enhanced predictive capabilities via thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl
B. Breeden, M. Poschmann and M.H.A. PiroNuclear Engineering and Design 419 112957 (2024)
https://doi.org/10.1016/j.nucengdes.2024.112957
Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments
Rajnikant V. Umretiya, Haozheng Qu, Liang Yin, Timothy B. Jurewicz, Vipul K. Gupta, Marija Drobnjak, Michael P. Knussman, Andrew K. Hoffman and Raul B. Rebaknpj Materials Degradation 8 (1) (2024)
https://doi.org/10.1038/s41529-024-00499-x
(2024)
https://doi.org/10.21203/rs.3.rs-4282779/v1
Improving the corrosion resistance of FeCrAl alloy in high temperature hydrogenated water through gaseous pre-oxidation
Jiayu Xie, Xin Ma and Wenjun KuangCorrosion Communications 15 36 (2024)
https://doi.org/10.1016/j.corcom.2024.03.001
Review of Construction Risks in a Nuclear Power Plant Environment
Eszter Horváth-Kálmán and Bakhtyar Saleh AhmmadYBL Journal of Built Environment 9 (1) 40 (2024)
https://doi.org/10.2478/jbe-2024-0005
Experimental and simulation studies to optimize the mechanical alloying process of ODS-FeCrAl alloy powder
Kangxue Li, Zhiqiang Xu, Wei Liu, Shufeng Yang, Kaixuan Gui, Peng Zhao and Jingshe LiJournal of Alloys and Compounds 176834 (2024)
https://doi.org/10.1016/j.jallcom.2024.176834
Chromium Coatings Applied to Zr Alloy Claddings by Cathodic Arc Ion Plating: Effect of Nitrogen Inclusion on Limiting Columnar Defects
Hae Won Yoon, Yuri Choi, Kuk Hyun Yeo, Sang Gweon Kim and Yong Ki ChoAdvanced Engineering Materials 26 (20) (2024)
https://doi.org/10.1002/adem.202400804
Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys
Atharva S Chikhalikar, Haozheng Qu, Hamdy Abouelella, Bhavani Nagothi, Rupesh Rajendran, Indranil Roy, Rajnikant Umretiya, Andrew Hoffman and Raul RebakJournal of Nuclear Materials 598 155179 (2024)
https://doi.org/10.1016/j.jnucmat.2024.155179
Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400 °C) and higher temperature (1200 °C) steam environments
Haozheng J. Qu, Atharva S. Chikhalikar, Hamdy Abouelella, Indranil Roy, Rupesh Rajendran, Bhavani S. Nagothi, Rajnikant Umretiya, Andrew K. Hoffman and Raul B. RebakCorrosion Science 229 111870 (2024)
https://doi.org/10.1016/j.corsci.2024.111870
Corrosion of Zircaloy-4, Zr-1Nb and FeCrAl alloys in deaerated water at 330 °C and 14 MPa: Superior corrosion resistance and corrosion mechanism of FeCrAl alloy by experiments and molecular dynamics simulations
Guanyu Jiang, Donghai Xu, Ya Wei, Huanteng Liu, Lu Liu and Wenjun KuangChemical Engineering Journal 462 142143 (2023)
https://doi.org/10.1016/j.cej.2023.142143
Effect of Al concentration on Fe-17Cr alloy during steam oxidation at 400 °C
Indranil Roy, Hamdy Abouelella, Rupesh Rajendran, Atharva S. Chikhalikar, Michael Larsen, Rajnikant Umretiya, Andrew Hoffman and Raul RebakCorrosion Science 217 111135 (2023)
https://doi.org/10.1016/j.corsci.2023.111135
Insights into oxidation and nitridation of alumina-forming FeCrAl alloy after supercritical water exposure: Effect of pre-corrosion on high-temperature damage behavior
Guanyu Jiang, Donghai Xu, Huanteng Liu, Bing He, Lu Liu, Yanhui Li and Jianqiao YangThe Journal of Supercritical Fluids 201 106007 (2023)
https://doi.org/10.1016/j.supflu.2023.106007
Risks and the management of construction in the environment of nuclear facilities
Eszter Horváth-Kálmán and Barbara ElekActa Technica Jaurinensis 16 (4) 143 (2023)
https://doi.org/10.14513/actatechjaur.00707
Multiphysics analysis of thermal mechanical behavior and tritium migration in FeCrAl and Cr-coated Zircaloy cladding under PWR normal operating and transient conditions
Liwen Yang, Rong Liu, Chenjie Qiu and Shengyu LiuProgress in Nuclear Energy 166 104942 (2023)
https://doi.org/10.1016/j.pnucene.2023.104942
(2023)
https://doi.org/10.2139/ssrn.4576728
Innovative Accident Tolerant Fuel Materials May Help Extending the Life of Light Water Reactors: A Perspective
Raul B. RebakCorrosion 79 (3) 328 (2023)
https://doi.org/10.5006/4181
(2023)
https://doi.org/10.2139/ssrn.4646885
Effect of surface oxides on tritium entrance and permeation in FeCrAl alloys for nuclear fuel cladding: a review
Yogendra S. Garud and Raul B. RebakCorrosion Reviews 41 (2) 143 (2023)
https://doi.org/10.1515/corrrev-2022-0033
Effect of nickel on the oxidation behavior of FeCrAl alloy in simulated PWR and BWR conditions
Haozheng J. Qu, Hamdy Abouelella, Atharva S. Chikhalikar, Rupesh Rajendran, Indranil Roy, Jonathan Priedeman, Rajnikant Umretiya, Andrew Hoffman, Janelle.P. Wharry and Raul RebakCorrosion Science 216 111093 (2023)
https://doi.org/10.1016/j.corsci.2023.111093
Energy Technology 2023
Patrick Shower, Scott Weaver, Voramon Dheeradhada, et al.The Minerals, Metals & Materials Series, Energy Technology 2023 15 (2023)
https://doi.org/10.1007/978-3-031-22638-0_2
Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review
Yogendra S. Garud, Andrew K. Hoffman and Raul B. RebakMetallurgical and Materials Transactions A 53 (3) 773 (2022)
https://doi.org/10.1007/s11661-021-06535-8
High Temperature Water Corrosion Behavior and In-Situ Electrochemical Analyses of Fe-13cr-4.5al-2mo-Xnb Alloys
Jingjing Liao, Hui Wang, Jun Wu, et al.SSRN Electronic Journal (2022)
https://doi.org/10.2139/ssrn.4005074
Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding
Shenyan Huang, Evan Dolley, Ke An, Dunji Yu, Cole Crawford, Michelle A. Othon, Ian Spinelli, Mike P. Knussman and Raul B. RebakJournal of Nuclear Materials 560 153524 (2022)
https://doi.org/10.1016/j.jnucmat.2022.153524
Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations
Lorenzo Malerba, Abderrahim Al Mazouzi, Marjorie Bertolus, Marco Cologna, Pål Efsing, Adrian Jianu, Petri Kinnunen, Karl-Fredrik Nilsson, Madalina Rabung and Mariano TarantinoEnergies 15 (5) 1845 (2022)
https://doi.org/10.3390/en15051845
Development of low-Cr wrought FeCrAl cladding alloys and its irradiation tolerance and steam oxidation resistance at 1200 °C
Hui Wang, Xiong Zhou, Hao He, Liping Guo, Yunxia Gao and Xuefei HuangCorrosion Science 195 109998 (2022)
https://doi.org/10.1016/j.corsci.2021.109998
Addition of Niobium in Fe-13cr-4.5al-2mo Alloy Used as Atf Cladding: Effect on High Temperature Water Corrosion and In-Situ Electrochemistry
Jingjing Liao, Hui Wang, Jun Wu, et al.SSRN Electronic Journal (2022)
https://doi.org/10.2139/ssrn.4077526
Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding
K.J. Evans and R.B. RebakCorrosion 78 (5) 449 (2022)
https://doi.org/10.5006/4018
Microstructural understanding of general and localized corrosion of Fe13Cr4Al2Mo1.2Nb alloy in high temperature aerated water and superheated steam
Xiaodong Lin, Xue Liang, Yifeng Li, Kun He, Peinan Du, Ruiqian Zhang and Ping ChenCorrosion Science 203 110341 (2022)
https://doi.org/10.1016/j.corsci.2022.110341
Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding
Raul B. Rebak, Timothy B. Jurewicz, Michael Larsen and Liang YinCorrosion Science 198 110156 (2022)
https://doi.org/10.1016/j.corsci.2022.110156
Insights into the superior stress corrosion cracking resistance of FeCrAl alloy in high temperature hydrogenated water: The critical role of grain boundary oxidation
Jiayu Xie, Shihao Zhang, Jiuyang Dong, Shengkai Wang, Hui Wang and Wenjun KuangCorrosion Science 208 110668 (2022)
https://doi.org/10.1016/j.corsci.2022.110668
Addition of niobium in Fe-13Cr-4.5Al-2Mo alloy used as ATF cladding: Effect on high temperature water corrosion and in-situ electrochemistry
Jingjing Liao, Hui Wang, Jun Wu, Wei Zhang, Fei Xu, Hongying Sun, Xuguang An and Shaoyu QiuMaterials & Design 220 110854 (2022)
https://doi.org/10.1016/j.matdes.2022.110854
On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors
Qian Xiao, Chaewon Kim, Changheui Jang, Chaewon Jeong, Hyunmyung Kim, Junjie Chen and Woong HeoJournal of Nuclear Materials 557 153265 (2021)
https://doi.org/10.1016/j.jnucmat.2021.153265
Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water
Fangqiang Ning, Xiang Wang, Ying Yang, Jibo Tan, Ziyu Zhang, Dan Jia, Xinqiang Wu and En-Hou HanJournal of Materials Science & Technology 70 136 (2021)
https://doi.org/10.1016/j.jmst.2020.07.026
Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8.6 UDGC
Jun Wang, Ryan Dailey, Zhehua Guo, Yukun Zhou, Paul Humrickhouse and Michael L. CorradiniNuclear Engineering and Design 371 110974 (2021)
https://doi.org/10.1016/j.nucengdes.2020.110974
Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors
Liang Yin, T.B. Jurewicz, M. Larsen, M. Drobnjak, C.C. Graff, D.R. Lutz and R.B. RebakJournal of Nuclear Materials 554 153090 (2021)
https://doi.org/10.1016/j.jnucmat.2021.153090
Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions
Nicholas R. Brown, Benton E. Garrison, Richard R. Lowden, M. Nedim Cinbiz and Kory D. LintonJournal of Nuclear Materials 539 152352 (2020)
https://doi.org/10.1016/j.jnucmat.2020.152352
Comprehensive Nuclear Materials
Kevin G. Field and Samuel A. BriggsComprehensive Nuclear Materials 293 (2020)
https://doi.org/10.1016/B978-0-12-803581-8.11613-3
Cold-rolling & annealing process for nuclear grade wrought FeCrAl cladding alloy to enhance the strength and ductility
Xuefei Huang, Hui Wang, Shaoyu Qiu, Yiyong Zhang, Kun He and Boda WuJournal of Materials Processing Technology 277 116434 (2020)
https://doi.org/10.1016/j.jmatprotec.2019.116434
https://doi.org/10.1016/B978-0-12-817503-3.00016-X
Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4
Rajnikant V. Umretiya, Barret Elward, Donghwi Lee, Mark Anderson, Raul B. Rebak and Jessika V. RojasJournal of Nuclear Materials 541 152420 (2020)
https://doi.org/10.1016/j.jnucmat.2020.152420
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding
Stephen S. Raiman, Kevin G. Field, Raul B. Rebak, Yukinori Yamamoto and Kurt A. TerraniJournal of Nuclear Materials 536 152221 (2020)
https://doi.org/10.1016/j.jnucmat.2020.152221
Intermediate temperature corrosion behaviour of Fe-12Cr-6Al-2Mo-0.2Si-0.03Y alloy (C26M) at 300–600 °C
Nan Li, Stephen S. Parker, Tarik A. Saleh, Stuart A. Maloy and Andrew T. NelsonCorrosion Science 157 274 (2019)
https://doi.org/10.1016/j.corsci.2019.05.029
231 (2019)
https://doi.org/10.1520/STP160920170145
Oxidation Characteristics of Two FeCrAl Alloys in Air and Steam from 800°C to 1300°C
Raul B. Rebak, Vipul K. Gupta and Michael LarsenJOM 70 (8) 1484 (2018)
https://doi.org/10.1007/s11837-018-2979-9
Impact toughness of commercial and model FeCrAl alloys
Zhiqian Sun, Yukinori Yamamoto and Xiang ChenMaterials Science and Engineering: A 734 93 (2018)
https://doi.org/10.1016/j.msea.2018.07.074