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Journal Articles

A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors

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Jinlei Zhao, Lixia He, Haocheng Zhao, Yuqi Zhang, Wentao Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031002.
Paper No: NERS-24-1087
https://doi.org/10.1115/1.4067824
Published Online: February 26, 2025
View Articletitled, A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors
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Topics: Errors, Fast neutron reactors, Fuels, Liquid metal fast breeder reactors, Neutrons, Regression models, Spent nuclear fuels, Uranium, Cooling, Simulation
Journal Articles

Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire

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Chenglu Zhao, Jialei Zhu, Fangtao Guo, Guixin Li, Congwei Li, Yushan Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021605.
Paper No: NERS-24-1059
https://doi.org/10.1115/1.4067263
Published Online: December 20, 2024
View Articletitled, Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire
Open the PDF for Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire in another window
Topics: Lasers, Maintenance, Stainless steel, Welded joints, Welding, Wire, Nuclear power stations, Corrosion, Ferrites (Magnetic materials), Spent fuel storage
Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

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Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.
Paper No: NERS-21-1018
https://doi.org/10.1115/1.4054514
Published Online: June 24, 2022
View Articletitled, Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
Open the PDF for Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool in another window
Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity
Journal Articles

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

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Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.
Paper No: NERS-21-1015
https://doi.org/10.1115/1.4051444
Published Online: March 15, 2022
View Articletitled, Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons
Journal Articles

Decay Heat Characterization for the European Sodium Fast Reactor

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Antonio Jiménez-Carrascosa, Nuria García-Herranz, Jiri Krepel, Marat Margulis, Una Baker, Eugene Shwageraus, Emil Fridman, Robert Gregg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011319.
Paper No: NERS-21-1051
https://doi.org/10.1115/1.4051798
Published Online: October 6, 2021
View Articletitled, Decay Heat Characterization for the European Sodium Fast Reactor
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Topics: Heat, Cooling
Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Open Access
Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.
Paper No: NERS-20-1204
https://doi.org/10.1115/1.4051292
Published Online: September 20, 2021
View Articletitled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

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Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.
Paper No: NERS-20-1080
https://doi.org/10.1115/1.4051723
Published Online: August 12, 2021
View Articletitled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels
Journal Articles

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

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Evaldas Bubelis, Michael Schikorr, 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): 011309.
Paper No: NERS-21-1048
https://doi.org/10.1115/1.4050563
Published Online: August 3, 2021
View Articletitled, Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor
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Topics: Rods, Sodium fast reactors, Transients (Dynamics), Cooling, Circuits, Flow (Dynamics)
Journal Articles

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

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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 Articletitled, 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

Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts

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Marek Ruščák, Tomáš Melichar, Jan Syblík, Otakar Frýbort, David Harut, Evžen Losa, Martin Mareček, Guido Mazzini, Mathieu Reungoat, Jan Pilát, Marek Benčik, Pavel Král
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021302.
Paper No: NERS-20-1077
https://doi.org/10.1115/1.4049715
Published Online: February 19, 2021
View Articletitled, Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts
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Topics: Circuits, Heat, Cooling, Fuels, Safety
Journal Articles

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

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David Rot, Jan Hrbek, Jakub Jirinec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602.
Paper No: NERS-20-1147
https://doi.org/10.1115/1.4048899
Published Online: November 16, 2020
View Articletitled, Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible
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Topics: Aluminum, Cooling, Design, Electromagnetic induction, Heat transfer, Melting, Temperature, Water, Inductors, Heat flux
Journal Articles

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

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Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.
Paper No: NERS-20-1009
https://doi.org/10.1115/1.4047495
Published Online: October 5, 2020
View Articletitled, Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
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Topics: Boundary-value problems, Computational fluid dynamics, Coolants, Flow (Dynamics), Geometry, Temperature, Cooling, Temperature distribution, Metals
Journal Articles

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

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Xiaocheng Fu, Fenglei Du, Xiang Pu, Xuan Wang, Fengze Han
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041101.
Paper No: NERS-19-1110
https://doi.org/10.1115/1.4048112
Published Online: September 4, 2020
View Articletitled, Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants
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Topics: Filters, Nuclear power stations, Tides, Water, Cooling, Safety, Design, Seas
Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

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Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.
Paper No: NERS-19-1164
https://doi.org/10.1115/1.4046910
Published Online: September 4, 2020
View Articletitled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment
Journal Articles

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

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René Manthey, Alexander Knospe, Carsten Lange, Christoph Schuster, Antonio Hurtado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021103.
Paper No: NERS-18-1135
https://doi.org/10.1115/1.4044846
Published Online: January 29, 2020
View Articletitled, Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions
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Topics: Pressure, Principal component analysis, Boiling, Stability, Cooling
Journal Articles

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

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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 Articletitled, 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

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

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Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.
Paper No: NERS-19-1001
https://doi.org/10.1115/1.4044847
Published Online: November 29, 2019
View Articletitled, RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test
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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models
Journal Articles

Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher

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Samyak S. Munot, Ganesh V, Parimal P. Kulkarni, Arun K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041206.
Paper No: NERS-18-1115
https://doi.org/10.1115/1.4043106
Published Online: July 19, 2019
View Articletitled, Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher
Open the PDF for Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher in another window
Topics: Ablation (Vaporization technology), Bricks, Cavities, Temperature, Thermocouples, Vessels, Water, Heat, Accidents, Floods
Journal Articles

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

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Kevin Schillo, Jason Cassibry, Mitchell Rodriguez, Seth Thompson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 042201.
Paper No: NERS-18-1025
https://doi.org/10.1115/1.4042710
Published Online: July 19, 2019
View Articletitled, Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion
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Topics: Heat conduction, Particulate matter, Plasmas (Ionized gases), Pressure, Radiation (Physics), Shock (Mechanics), Simulation, Temperature, Viscosity, Vortices
Journal Articles

Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime

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J. Lupiano Contreras, A. S. Doval, P. A. Alberto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020902.
Paper No: NERS-18-1063
https://doi.org/10.1115/1.4042363
Published Online: March 15, 2019
View Articletitled, Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime
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Topics: Design, Flow (Dynamics), Uncertainty, Cooling, Heat transfer coefficients