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Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haileyesus Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011301.
Paper No: NERS-20-1056
https://doi.org/10.1115/1.4048905
Published Online: July 20, 2021
View Article titled, Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results
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Topics: Modeling, Safety, Scram, Sodium, Sodium fast reactors, Temperature, Fuels, Design, Computers, Equilibrium (Physics)
Journal Articles

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

Kai Kosowski, Marcus Seidl
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021107.
Paper No: NERS-19-1028
https://doi.org/10.1115/1.4045034
Published Online: January 29, 2020
View Article titled, External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
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Topics: Accidents, Coolants, Cooling, Diesel engines, Emergencies, Flow (Dynamics), Hazards, Heat, Leakage, Pressure
Journal Articles

Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031702.
Paper No: NERS-17-1229
https://doi.org/10.1115/1.4042541
Published Online: May 3, 2019
View Article titled, Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System
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Topics: Clearances (Engineering), Cylinders, Design, Flow (Dynamics), Fuels, Hydraulic drive systems, Pressure, Scram, Temperature, Water
Journal Articles

Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

Gueorgui I. Petkov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020905.
Paper No: NERS-16-1133
https://doi.org/10.1115/1.4039000
Published Online: March 5, 2018
View Article titled, Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events
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Topics: Accidents, Design, Errors, Safety, Scram, Transients (Dynamics), Water, Pressure, Delays, Valves
Journal Articles

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.
Paper No: NERS-16-1007
https://doi.org/10.1115/1.4034478
Published Online: December 20, 2016
View Article titled, A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
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Topics: Heat flux, Nucleate boiling, Pressurized water reactors, Rods, Safety, Scram, Spacetime, Thermal hydraulics, Transients (Dynamics), Temperature profiles
Journal Articles

Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

Csaba Maráczy, György Hegyi, István Trosztel, Emese Temesvári
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011004.
Paper No: NERS-15-1041
https://doi.org/10.1115/1.4030933
Published Online: December 9, 2015
View Article titled, Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor
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Topics: Fuels, Nuclear fuels, Safety, Scram, Temperature, Water, Pressure, Steady state, Test facilities, Fuel rods