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Journal Articles

Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3

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Jacob Yankey, Marisa Monreal, Matt Jackson, Michael Simpson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030906.
Paper No: NERS-23-1066
https://doi.org/10.1115/1.4064598
Published Online: March 8, 2024
View Articletitled, Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3
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Topics: Circuits, Electrodes, Molten salt reactors, Temperature, Zirconium, Electrodeposition, Rods, Electrons
Journal Articles

Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor

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Shujun Wang, Xianmin Huang, Yanfei Rao, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021402.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: January 29, 2024
View Articletitled, Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor
Open the PDF for Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor in another window
Topics: Boilers, Design, Flow (Dynamics), Pressure, Pressurized water reactors, Small modular reactors, Temperature, Thermal hydraulics, Oscillations, Junctions
Journal Articles

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

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Joel Guidez, Janos Bodi, Konstantin Mikityuk, 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): 011323.
Paper No: NERS-21-1043
https://doi.org/10.1115/1.4052589
Published Online: October 29, 2021
View Articletitled, Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
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Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization
Journal Articles

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

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Janos Bodi, Alexander Ponomarev, Evaldas Bubelis, 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): 011315.
Paper No: NERS-21-1047
https://doi.org/10.1115/1.4052190
Published Online: September 20, 2021
View Articletitled, Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout
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Topics: Heat, Simulation, Sodium, Temperature, Design, Circuits, Flow (Dynamics)
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

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

The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3

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Pavel Kůs, Martin Kronďák, Martin Skala, Alena Kobzová, Petr Brabec, Patricie Halodová, Janka Mihóková, Štefan Tkáč, Anna Černá
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021804.
Paper No: NERS-20-1149
https://doi.org/10.1115/1.4049281
Published Online: January 28, 2021
View Articletitled, The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3
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Topics: Circuits, Nuclear power stations, Hydrogen, Magnetite, Water, Microscopy
Journal Articles

Detection of Neutrons Emitted From Reactor Primary Circuit Water by Discontinuing Flow Method

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L. Viererbl, A. Kolros, M. Vinš, V. Klupák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024508.
Paper No: NERS-20-1075
https://doi.org/10.1115/1.4048240
Published Online: November 16, 2020
View Articletitled, Detection of Neutrons Emitted From Reactor Primary Circuit Water by Discontinuing Flow Method
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Topics: Circuits, Flow (Dynamics), Neutrons, Water, Radioisotopes, Containers, Sensors
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

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Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Articletitled, A Simplified Two-Group Multipoint Kinetics Model
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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics
Journal Articles

Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger

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Angel Papukchiev
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021104.
Paper No: NERS-19-1029
https://doi.org/10.1115/1.4045074
Published Online: January 29, 2020
View Articletitled, Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
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Topics: Flow (Dynamics), Fluids, Heat exchangers, Heat transfer, Modeling, Simulation, Temperature, Transients (Dynamics), Turbulence, Computational fluid dynamics
Journal Articles

Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO 2 Brayton Cycle

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Xiao Long Li, G. H. Tang, Yuan Hong Fan, Dan Lei Yang, Si Qi Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041303.
Paper No: NERS-18-1075
https://doi.org/10.1115/1.4043098
Published Online: July 19, 2019
View Articletitled, Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO 2 Brayton Cycle
Open the PDF for Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO 2 Brayton Cycle in another window
Topics: Fins, Flow (Dynamics), Heat transfer, Supercritical carbon dioxide, Heat exchangers, Circuits, Brayton cycle
Journal Articles

Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

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Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030301.
Paper No: NERS-19-1035
https://doi.org/10.1115/1.4043382
Published Online: April 19, 2019
View Articletitled, Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018
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Topics: Accidents, Circuits, Coolants, Corrosion, Generation IV reactors, Materials research, Modeling, Nuclear engineering, Nuclear fuel cycle, Nuclear reactors
Journal Articles

Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit

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Petr Samek, Ondřej Chocholatý, Zdeněk Čančura, Antonín Kříž
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030907.
Paper No: NERS-18-1117
https://doi.org/10.1115/1.4043105
Published Online: April 16, 2019
View Articletitled, Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit
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Topics: Circuits, Coatings, Corrosion, Corrosion resistance, Steel, Welded joints, Testing, Coating processes
Journal Articles

Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap

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Nicolás Alejandro Malinovsky
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020915.
Paper No: NERS-18-1064
https://doi.org/10.1115/1.4042361
Published Online: March 15, 2019
View Articletitled, Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap
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Topics: Circuits, Electricity (Physics), Nuclear power stations, Stress, Power systems (Machinery), Modeling, Computer software, Flow (Dynamics), Electronic systems
Journal Articles

Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant

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Massimo Di Pietro, Sergio Pistelli, Eugenio Garneri, Rosa Lo Frano, Riccardo Ciolini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020910.
Paper No: NERS-16-1125
https://doi.org/10.1115/1.4038556
Published Online: March 5, 2018
View Articletitled, Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant
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Topics: Circuits, Ejectors, Flow (Dynamics), Nuclear decommissioning, Nuclear power stations, Scrap metals, Suction, Water, Heat shielding
Journal Articles

Iodine Benchmarks in the SARNET Network of Excellence

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Tim Haste, Mirco Di Giuli, Gunter Weber, Sebastian Weber
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021022.
Paper No: NERS-15-1026
https://doi.org/10.1115/1.4031652
Published Online: February 29, 2016
View Articletitled, Iodine Benchmarks in the SARNET Network of Excellence
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Topics: Chemistry, Circuits, Containment, Uncertainty, Aerosols, Flow (Dynamics), Steel, Water, Thermal hydraulics, Modeling
Journal Articles

Design of an In-Pile SCWR Fuel Qualification Test Loop

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Ales Vojacek, Mariana Ruzickova, Thomas Schulenberg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011003.
Paper No: NERS-15-1054
https://doi.org/10.1115/1.4030872
Published Online: December 9, 2015
View Articletitled, Design of an In-Pile SCWR Fuel Qualification Test Loop
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Topics: Circuits, Coolants, Design, Fuel rods, Fuels, Manufacturing, Pressure, Safety, Supercritical water reactors, Temperature