[1]
Sebastien Dryepondt, Kinga A. Unocic, David T. Hoelzer, Caleb P. Massey, Bruce A. Pint, Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding, Journal of Nuclear Materials 501 (2018) 59-71.
DOI: 10.1016/j.jnucmat.2017.12.035
Google Scholar
[2]
Raul B. Rebak, Kurt A. Terrani, Russ M. Fawcett, FeCrAl alloys for accident tolerant fuel cladding in light water reactors, Proceedings of the ASME 2016 Pressure Vessels and Piping Conference, PVP2016-63162.
DOI: 10.1115/pvp2016-63162
Google Scholar
[3]
Tim Gräning, Michael Rieth, Anton Möslang, Alexei Kuzmin, Andris Anspoks, Janis Timoshenko, Arturs Cintins, Juris Purans, Investigation of precipitate in an austenitic ODS steel containing a carbon-rich process control agent, Nuclear Materials and Energy 15 (2018) 237–243.
DOI: 10.1016/j.nme.2018.05.005
Google Scholar
[4]
Zhonglian Bai, Linbo Wang, Chenxi Wang, Wenhua Gao, Lefu Zhang, Tong Liu, Corrosion behavior of ferritic ODS steel prepared by adding YH2 nanoparticles in supercritical water at 600 °C, Progress in Natural Science: Materials International 28 (2018) 505–509.
DOI: 10.1016/j.pnsc.2018.07.008
Google Scholar
[5]
E. Macía, A. García-Junceda, M. Serrano, S.J. Hong, M. Campos, Effect of mechanical alloying on the microstructural evolution of a ferritic ODS steel with (YeTieAleZr) addition processed by Spark Plasma Sintering (SPS), Nuclear Engineering and Technology 53 (2021) 2582-2590.
DOI: 10.1016/j.net.2021.02.002
Google Scholar
[6]
Frank Bergner, Isabell Hilger, Jouko Virta, Juha Lagerbom, Gunter Gerbeth, Sarah Connolly, Zuliang Hong, Patrick S. Grant, Thomas Weissgärbe, Alternative Fabrication Routes toward Oxide-Dispersion-Strengthened Steels and Model Alloys, Metallurgical And Materials Transactions A,.
DOI: 10.1007/s11661-016-3616-2
Google Scholar
[7]
Mohammad Amin Moghadasi, Mahmoud Nili-Ahmadabadi, Farsad Forghani, Hyoung Seop Kim, Development of an oxide dispersion-strengthened steel by introducing oxygen carrier compound into the melt aided by a general thermodynamic model, Springer Nature (2016) Sci. Rep. 6, 38621;.
DOI: 10.1038/srep38621
Google Scholar
[8]
Massimo De Sanctis, Alessandra Fava, Gianfranco Lovicu, Roberto Montanari, Maria Richetta, Claudio Testani, Alessandra Varone, Mechanical Characterization of a Nano-ODS Steel Prepared by Low-Energy Mechanical Alloying, Metals (2017) 7, 283;.
DOI: 10.3390/met7080283
Google Scholar
[9]
Chenyang Lu, Zheng Lu, Xu Wang, Rui Xie, Zhengyuan Li, Michael Higgins, Chunming Liu, Fei Gao, Lumin Wang, Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation, Springer Nature (2017) Sci. Rep. 7, 40343;.
DOI: 10.1038/srep40343
Google Scholar
[10]
Jianqiang Wang, Sheng Liu, Bin Xu, Jianyang Zhang, Mingyue Sun, Dianzhong Li, Research progress on preparation technology of oxide dispersion strengthened steel for nuclear energy, Int. J. Extrem. Manuf. 3 (2021) 032001.
DOI: 10.1088/2631-7990/abff1a
Google Scholar
[11]
Ludek Stratil, Vít Horník, Petr Dymáˇcek, Pavla Roupcová and Jiˇrí Svoboda, The Influence of Aluminum Content on Oxidation Resistance of New-Generation ODS Alloy at 1200 °C, Metals (2020), 10, 1478;.
DOI: 10.3390/met10111478
Google Scholar
[12]
Jianjie Wang, Dijun Long, Liming Yu, Yongchang Liu, Huijun Li, Zumin Wang, Influence of Al addition on the microstructure and, mechanical properties of Zr-containing 9Cr-ODS steel, Journal of Materials Research and Technology (2021), 1 3: 1698 -1708.
DOI: 10.1016/j.jmrt.2021.05.112
Google Scholar
[13]
K. Kondo, S. Aoki, S. Yamashita, S. Ukai, K. Sakamoto, M. Hirai, A. Kimura, Ion irradiation effects on FeCrAl-ODS ferritic steel, Nuclear Materials and Energy 15 (2018) 13–16.
DOI: 10.1016/j.nme.2018.05.022
Google Scholar
[14]
Yoosung H, Akihiko Kimura, Effect of Cold Rolling on Recrystallization Behavior of Al-Free and Al-Added 15Cr-ODS Ferritic Steels, Crystals (2019), 9, 145;.
DOI: 10.3390/cryst9030145
Google Scholar
[15]
Aravind Murugan, R. Sai Santhosh, Ravikumar Raju, A.K. Lakshminarayanan, Shaju K. Albert, Dissimilar and Similar Laser Beam and GTA Welding of Nuclear Fuel Pin Cladding Tube to End Plug Joint, Advanced Engineering Forum Submitted: 2017-07-23 ISSN: 2234-991X, Vol. 24, pp.40-47,.
DOI: 10.4028/www.scientific.net/aef.24.40
Google Scholar