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Journal Articles

“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”

Shu Jun Wang, Xianmin Huang, Yanfei Rao, Blair Bromley

ASME J of Nuclear Rad Sci.

Paper No: NERS-23-1086

https://doi.org/10.1115/1.4063240

Published Online: August 24, 2023

View Article titled, “Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”

Topics: Pressurized water reactors, Small modular reactors, Testing, Thermal hydraulics, Flow (Dynamics), Oscillations, Boilers, Design, Circuits, Heat transfer

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

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

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

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 Article titled, Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

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

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

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

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

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

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

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

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

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

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 Article titled, A Simplified Two-Group Multipoint Kinetics Model

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

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

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

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

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

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 Article titled, 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

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 Article titled, Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit

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

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 Article titled, Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap

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

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 Article titled, 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

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 Article titled, 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

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 Article titled, Design of an In-Pile SCWR Fuel Qualification Test Loop

Topics: Circuits, Coolants, Design, Fuel rods, Fuels, Manufacturing, Pressure, Safety, Supercritical water reactors, Temperature

Journal citation

NARROW

Manuscript

“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”

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

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

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

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

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

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

A Simplified Two-Group Multipoint Kinetics Model

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

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

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

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

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

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

Iodine Benchmarks in the SARNET Network of Excellence

Design of an In-Pile SCWR Fuel Qualification Test Loop

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