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Journal Articles

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.
Paper No: NERS-20-1021
https://doi.org/10.1115/1.4050211
Published Online: April 16, 2021
View Article titled, Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis
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Topics: Condensation, Cooling, Design, Flow (Dynamics), Heat transfer, Steam, Test facilities, Temperature, Pressure, Water
Journal Articles

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, A. K. Vishnoi, Vikas Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041205.
Paper No: NERS-18-1093
https://doi.org/10.1115/1.4043198
Published Online: July 19, 2019
View Article titled, Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor
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Topics: Boiling water reactors, Condensers (steam plant), Coolants, Design, Flow (Dynamics), Heat, Pressure, Safety, Temperature, Test facilities
Journal Articles

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203.
Paper No: NERS-18-1079
https://doi.org/10.1115/1.4042852
Published Online: July 19, 2019
View Article titled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
Open the PDF for Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor in another window
Topics: Heat, Test facilities, Water, Cavities, Earthquakes, Heat sinks, Boiling water reactors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Fracture (Materials)
Journal Articles

Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020902.
Paper No: NERS-16-1115
https://doi.org/10.1115/1.4038059
Published Online: March 5, 2018
View Article titled, Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes
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Topics: Aerosols, Containment, Nuclear fission, Temperature, Sensitivity analysis, Water, Condensers (steam plant), Thermal hydraulics, Condensation
Journal Articles

Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis

Jia Yang, Rongyong Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014501.
Paper No: NERS-15-1137
https://doi.org/10.1115/1.4035285
Published Online: December 20, 2016
View Article titled, Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis
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Topics: Condensers (steam plant), Cooling, Optimization, Sensitivity analysis, Steam turbines, Design, Nuclear power stations, Tariffs, Cooling towers, Pipes