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Journal Articles

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

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011323.
Paper No: NERS-21-1043
DOI: https://doi.org/10.1115/1.4052589
Published Online: October 29, 2021
View Article titled, 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

Janos Bodi, Alexander Ponomarev, Evaldas Bubelis, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011315.
Paper No: NERS-21-1047
DOI: https://doi.org/10.1115/1.4052190
Published Online: September 20, 2021
View Article titled, 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

Evaldas Bubelis, Michael Schikorr, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011309.
Paper No: NERS-21-1048
DOI: https://doi.org/10.1115/1.4050563
Published Online: August 3, 2021
View Article titled, 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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021302.
Paper No: NERS-20-1077
DOI: https://doi.org/10.1115/1.4049715
Published Online: February 19, 2021
View Article titled, 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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021804.
Paper No: NERS-20-1149
DOI: https://doi.org/10.1115/1.4049281
Published Online: January 28, 2021
View Article titled, 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

L. Viererbl, A. Kolros, M. Vinš, V. Klupák
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024508.
Paper No: NERS-20-1075
DOI: https://doi.org/10.1115/1.4048240
Published Online: November 16, 2020
View Article titled, 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

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
DOI: https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Article titled, 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

Angel Papukchiev
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021104.
Paper No: NERS-19-1029
DOI: https://doi.org/10.1115/1.4045074
Published Online: January 29, 2020
View Article titled, 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

Xiao Long Li, G. H. Tang, Yuan Hong Fan, Dan Lei Yang, Si Qi Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041303.
Paper No: NERS-18-1075
DOI: https://doi.org/10.1115/1.4043098
Published Online: July 19, 2019
View Article titled, Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO 2 Brayton Cycle
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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

Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030301.
Paper No: NERS-19-1035
DOI: https://doi.org/10.1115/1.4043382
Published Online: April 19, 2019
View Article titled, Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018
Click here to open pdf in another window PDF for Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018
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

Petr Samek, Ondřej Chocholatý, Zdeněk Čančura, Antonín Kříž
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030907.
Paper No: NERS-18-1117
DOI: https://doi.org/10.1115/1.4043105
Published Online: April 16, 2019
View Article titled, 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

Nicolás Alejandro Malinovsky
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020915.
Paper No: NERS-18-1064
DOI: https://doi.org/10.1115/1.4042361
Published Online: March 15, 2019
View Article titled, 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

Massimo Di Pietro, Sergio Pistelli, Eugenio Garneri, Rosa Lo Frano, Riccardo Ciolini
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020910.
Paper No: NERS-16-1125
DOI: https://doi.org/10.1115/1.4038556
Published Online: March 5, 2018
View Article titled, Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant
Click here to open pdf in another window PDF for Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant
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

Tim Haste, Mirco Di Giuli, Gunter Weber, Sebastian Weber
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021022.
Paper No: NERS-15-1026
DOI: https://doi.org/10.1115/1.4031652
Published Online: February 29, 2016
View Article titled, Iodine Benchmarks in the SARNET Network of Excellence
Click here to open pdf in another window PDF for Iodine Benchmarks in the SARNET Network of Excellence
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

Ales Vojacek, Mariana Ruzickova, Thomas Schulenberg
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011003.
Paper No: NERS-15-1054
DOI: https://doi.org/10.1115/1.4030872
Published Online: December 9, 2015
View Article titled, 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