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Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

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Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.
Paper No: NERS-17-1163
https://doi.org/10.1115/1.4040887
Published Online: September 10, 2018
View Articletitled, Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
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Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations
Journal Articles

The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

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Jun Wang, Yuqiao Fan, Yapei Zhang, Xinghe Ni, Wenxi Tian, Michael L. Corradini, Guanghui Su, Suizheng Qiu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021002.
Paper No: NERS-15-1009
https://doi.org/10.1115/1.4031842
Published Online: February 29, 2016
View Articletitled, The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA
Open the PDF for The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA in another window
Topics: Accidents, Flow (Dynamics), Temperature, Vessels, Melting, Hydrogen