EDP Sciences logo
Submit your paper
Search
Menu
All issues EPJ Nuclear Sci. Technol., 3 (2017) 34 Article references

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:

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 Huang
Surface and Coatings Technology 498 131783 (2025)
https://doi.org/10.1016/j.surfcoat.2025.131783

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 Wu
Journal of Nuclear Materials 603 155454 (2025)
https://doi.org/10.1016/j.jnucmat.2024.155454

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 Umretiya
Corrosion Science 252 112965 (2025)
https://doi.org/10.1016/j.corsci.2025.112965

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. Sirak
Problems of Atomic Science and Technology 27 (2025)
https://doi.org/10.46813/2025-156-027

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 Mu
Processes 13 (6) 1661 (2025)
https://doi.org/10.3390/pr13061661

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 Charit
Progress in Nuclear Energy 173 105257 (2024)
https://doi.org/10.1016/j.pnucene.2024.105257

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 Olsson
Journal of Materiomics 10 (4) 937 (2024)
https://doi.org/10.1016/j.jmat.2024.02.007

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. Rebak
Corrosion Science 229 111870 (2024)
https://doi.org/10.1016/j.corsci.2024.111870

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 Qiu
Reliability Engineering & System Safety 243 109847 (2024)
https://doi.org/10.1016/j.ress.2023.109847

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 Rebak
Journal of Nuclear Materials 598 155179 (2024)
https://doi.org/10.1016/j.jnucmat.2024.155179

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. Rebak
Journal of Nuclear Materials 588 154751 (2024)
https://doi.org/10.1016/j.jnucmat.2023.154751

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 Cho
Advanced Engineering Materials 26 (20) (2024)
https://doi.org/10.1002/adem.202400804

Review of Construction Risks in a Nuclear Power Plant Environment

Eszter Horváth-Kálmán and Bakhtyar Saleh Ahmmad
YBL 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 Li
Journal of Alloys and Compounds 176834 (2024)
https://doi.org/10.1016/j.jallcom.2024.176834

Improving the corrosion resistance of FeCrAl alloy in high temperature hydrogenated water through gaseous pre-oxidation

Jiayu Xie, Xin Ma and Wenjun Kuang
Corrosion Communications 15 36 (2024)
https://doi.org/10.1016/j.corcom.2024.03.001

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. Rebak
npj Materials Degradation 8 (1) (2024)
https://doi.org/10.1038/s41529-024-00499-x

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. Piro
Nuclear Engineering and Design 419 112957 (2024)
https://doi.org/10.1016/j.nucengdes.2024.112957

Effect of nickel on the oxidation behavior of FeCrAl alloy in simulated PWR and BWR conditions

Haozheng J. Qu, Hamdy Abouelella, Atharva S. Chikhalikar, et al.
Corrosion Science 216 111093 (2023)
https://doi.org/10.1016/j.corsci.2023.111093

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 Liu
Progress in Nuclear Energy 166 104942 (2023)
https://doi.org/10.1016/j.pnucene.2023.104942

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 Kuang
Chemical Engineering Journal 462 142143 (2023)
https://doi.org/10.1016/j.cej.2023.142143

Haozheng J. Qu, Atharva Chikhalikar, Hamdy Abouelella, Indranil Roy, Rupesh Rajendran, Bhavani S. Nagothi, Rajnikant Umretiya, Dr. Andrew Hoffman and Raul Rebak
(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. Rebak
Corrosion 79 (3) 328 (2023)
https://doi.org/10.5006/4181

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 Yang
The Journal of Supercritical Fluids 201 106007 (2023)
https://doi.org/10.1016/j.supflu.2023.106007

Effect of surface oxides on tritium entrance and permeation in FeCrAl alloys for nuclear fuel cladding: a review

Yogendra S. Garud and Raul B. Rebak
Corrosion Reviews 41 (2) 143 (2023)
https://doi.org/10.1515/corrrev-2022-0033

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, et al.
Corrosion Science 195 109998 (2022)
https://doi.org/10.1016/j.corsci.2021.109998

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, et al.
Corrosion Science 208 110668 (2022)
https://doi.org/10.1016/j.corsci.2022.110668

Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review

Yogendra S. Garud, Andrew K. Hoffman and Raul B. Rebak
Metallurgical and Materials Transactions A 53 (3) 773 (2022)
https://doi.org/10.1007/s11661-021-06535-8

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 Tarantino
Energies 15 (5) 1845 (2022)
https://doi.org/10.3390/en15051845

Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding

Raul B. Rebak, Timothy B. Jurewicz, Michael Larsen and Liang Yin
Corrosion Science 198 110156 (2022)
https://doi.org/10.1016/j.corsci.2022.110156

Hydrogen Permeation in FeCrAl APMT Alloy for Accident Tolerant Fuel Cladding

K.J. Evans and R.B. Rebak
Corrosion 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, et al.
Corrosion Science 203 110341 (2022)
https://doi.org/10.1016/j.corsci.2022.110341

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

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

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 Qiu
Materials & Design 220 110854 (2022)
https://doi.org/10.1016/j.matdes.2022.110854

Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding

Shenyan Huang, Evan Dolley, Ke An, et al.
Journal of Nuclear Materials 560 153524 (2022)
https://doi.org/10.1016/j.jnucmat.2022.153524

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, et al.
Journal 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, et al.
Journal 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, et al.
Nuclear 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, et al.
Journal of Nuclear Materials 554 153090 (2021)
https://doi.org/10.1016/j.jnucmat.2021.153090

Cold-rolling & annealing process for nuclear grade wrought FeCrAl cladding alloy to enhance the strength and ductility

Xuefei Huang, Hui Wang, Shaoyu Qiu, et al.
Journal of Materials Processing Technology 277 116434 (2020)
https://doi.org/10.1016/j.jmatprotec.2019.116434

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. Linton
Journal of Nuclear Materials 539 152352 (2020)
https://doi.org/10.1016/j.jnucmat.2020.152352

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. Terrani
Journal of Nuclear Materials 536 152221 (2020)
https://doi.org/10.1016/j.jnucmat.2020.152221

Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4

Rajnikant V. Umretiya, Barret Elward, Donghwi Lee, et al.
Journal of Nuclear Materials 541 152420 (2020)
https://doi.org/10.1016/j.jnucmat.2020.152420

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. Nelson
Corrosion Science 157 274 (2019)
https://doi.org/10.1016/j.corsci.2019.05.029