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Carlo Parisi, Zhegang Ma, Diego Mandelli, Nolan Anderson & Hongbin Zhang. (2020) Risk-Informed Safety Analysis for Accident Tolerant Fuels. Nuclear Science and Engineering 194:8-9, pages 748-770.
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J. Wang, H. Yeom, P. Humrickhouse, K. Sridharan & M. Corradini. (2020) Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event. Nuclear Technology 206:3, pages 467-477.
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Una Baker, Yong-Joon Choi, Nicholas Rollins, Khang Nguyen, WooHyun Jung, Abe Whitmeyer, Jason Hou & Ben Lindley. (2024) Source term analysis of FeCrAl accident tolerant fuel using MELCOR. Annals of Nuclear Energy 202, pages 110482.
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Ilyas Khurshid, Yacine Addad & Imran Afgan. (2024) Study on corium-concrete interaction, heat transfer, and concrete ablation: Impact of replacing Zircaloy cladding with accident tolerant silicon carbide cladding on corium characteristics. Applied Thermal Engineering 243, pages 122569.
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Cole Dunbar. 2024. Nuclear Power Reactor Designs. Nuclear Power Reactor Designs
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Maithah Alaleeli, Yongsun Yi, Ali Alraisi, Suwon Lee, Andreas Schiffer, Saeed A. Alameri & Ahmed Alkaabi. (2023) The effects of cladding thermo-physical and thermo-chemical properties on the coping time during a PWR unmitigated LB-LOCA. Progress in Nuclear Energy 162, pages 104783.
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S. Ramezani & M. Aghaie. (2023) Neutronic and Thermal hydraulic evaluation of accident tolerant cladding materials in a WWER1000. Progress in Nuclear Energy 161, pages 104708.
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Nan Zhao, Weimin Ma & Sevostian Bechta. (2023) A review of the assessment of severe accident management guidelines and actions through analytical simulations. Annals of Nuclear Energy 180, pages 109448.
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Zehua Guo, Ryan Dailey, Yukun Zhou, Zhongning Sun, Jun Wang & Michael L. Corradini. (2021) Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout. Nuclear Engineering and Design 372, pages 110979.
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Jun Wang, Ryan Dailey, Zhehua Guo, Yukun Zhou, Paul Humrickhouse & Michael L. Corradini. (2021) Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8.6 UDGC. Nuclear Engineering and Design 371, pages 110974.
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Chaewon Kim, Hyunmyung Kim, Changheui Jang, Kangsan Kim, Yonghee Kim, Seungjae Lee & Hun Jang. (2019) Feasibility assessment of the alumina‐forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors. International Journal of Energy Research 44:10, pages 8074-8088.
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Tangtao Feng, Jun Wang, Yimin Zhou, Ping Song, Mingjun Wang, Ryan Dailey, Wenxi Tian & Michael L. Corradini. (2020) Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out. Nuclear Engineering and Design 363, pages 110678.
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Peizheng Hu, Guangliang Chen, Zhaofei Tian, Huilun Kang, Yuguan Jin & Thompson Appah. (2020) Investigating on multi-RANS models coupling simulation for flow mixing experiments. Annals of Nuclear Energy 142, pages 107389.
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Koroush Shirvan. (2020) Implications of accident tolerant fuels on thermal-hydraulic research. Nuclear Engineering and Design 358, pages 110432.
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Bowen Qiu, Jun Wang, Yangbin Deng, Mingjun Wang, Yingwei Wu & S.Z. Qiu. (2020) A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding. Nuclear Engineering and Technology 52:1, pages 1-13.
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Haoran Ju, Mingjun Wang, Chong Chen, Xiaohan Zhao, Minfu Zhao, Wenxi Tian, G.H. Su & Suizheng Qiu. (2019) Numerical study on the turbulent mixing in channel with Large Eddy Simulation (LES) using spectral element method. Nuclear Engineering and Design 348, pages 169-176.
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J. Zhang, H. Yu, M.J. Wang, Y.W. Wu, W.X. Tian, S.Z. Qiu & G.H. Su. (2019) Experimental study on the flow and thermal characteristics of two-phase leakage through micro crack. Applied Thermal Engineering 156, pages 145-155.
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Amar Aliche, Hocine Hammoum & Karima Bouzelha. (2019) Mecano-reliability analysis applied to RC tank under seismic loads according to the Algerian seismic standard. Asian Journal of Civil Engineering 20:3, pages 395-408.
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Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su & Michael L. Corradini. (2018) Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant. Journal of Nuclear Engineering and Radiation Science 4:4.
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