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Journal Articles

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

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 Article titled, 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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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

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 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

Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

Muhammad Aadil, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021801.
Paper No: NERS-20-1210
https://doi.org/10.1115/1.4051618
Published Online: October 19, 2021
View Article titled, Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator
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Topics: Aerosols, Boilers, Decontamination, Nuclides, Particulate matter, Pressurized water reactors, Turbulence, Computational fluid dynamics, Flow (Dynamics), Particle size
Journal Articles

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Jeremy Bittan, Clement Bore, Joel Guidez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041301.
Paper No: NERS-20-1079
https://doi.org/10.1115/1.4048991
Published Online: April 16, 2021
View Article titled, Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions
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Topics: Boilers, Heat, Reactor vessels, Sodium, Temperature, Vessels, Shells, Design, Energy budget (Physics), Pumps
Journal Articles

Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

Vasilii Volkov, Luka Golibrodo, Alexey Krutikov, Oleg Kudryavtsev, Yurii Nadinskii, Alexander Skibin, Vladimir Sotskov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031403.
Paper No: NERS-19-1162
https://doi.org/10.1115/1.4048234
Published Online: February 19, 2021
View Article titled, Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics
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Topics: Flow (Dynamics), Nozzles, Steam, Evaporation, Boilers, Optimization
Journal Articles

Three-Dimensional Profilometry Utilization on VVER Type Reactors

Jaroslav Brom, Jan Patera, Pavel Zahrádka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024501.
Paper No: NERS-20-1115
https://doi.org/10.1115/1.4048237
Published Online: October 30, 2020
View Article titled, Three-Dimensional Profilometry Utilization on VVER Type Reactors
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Topics: Boilers, Reactor vessels, Lasers, Shapes, Nuclear power stations, Water
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

VVER 1000 Severe Accident Analyses Using MELCOR Code

Marek Ruščák, Guido Mazzini, Milos Kynčl, Sevastyan Savanyuk, Miroslav Hrehor, Alis Musa, Alain Flores y Flores
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030913.
Paper No: NERS-18-1086
https://doi.org/10.1115/1.4043378
Published Online: April 19, 2019
View Article titled, VVER 1000 Severe Accident Analyses Using MELCOR Code
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Topics: Accidents, Containment, Pressure, Water, Temperature, Nuclear fission, Failure, Leakage, Boilers
Journal Articles

Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ -Ray Counting

Patricia Schindler, Pierre Guy Allinei, Laurent Loubet, Veronique Pointeau
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020912.
Paper No: NERS-18-1056
https://doi.org/10.1115/1.4042851
Published Online: March 15, 2019
View Article titled, Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ -Ray Counting
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Topics: Boilers, Modeling, Noise (Sound), Sensors, Fluids, Control systems, Crystals, Signals
Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.
Paper No: NERS-17-1163
https://doi.org/10.1115/1.4040887
Published Online: September 10, 2018
View Article titled, Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
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Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations
Journal Articles

Thermo-Economic Performance of a Cogeneration Medium–Small Modular Nuclear Reactor Plant in Canada

Gaoming Ge, Tomohiko Ikegawa, Koji Nishida, Carey J. Simonson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031002.
Paper No: NERS-16-1052
https://doi.org/10.1115/1.4035335
Published Online: May 25, 2017
View Article titled, Thermo-Economic Performance of a Cogeneration Medium–Small Modular Nuclear Reactor Plant in Canada
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Topics: Boilers, Combined heat and power, Heat, High temperature, Electric power generation, Natural gas, Steam, Carbon
Journal Articles

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Thambiayah Nitheanandan, X. Cao, J.-H. Choi, D. Dupleac, D.-H. Kim, H. G. Lele, A. K. Nayak, H. P. Rammohan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020903.
Paper No: NERS-16-1084
https://doi.org/10.1115/1.4035726
Published Online: March 1, 2017
View Article titled, Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
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Topics: Accidents, Heat, Vessels, Water, Heavy water reactors, Computers, Pressure, Fuels, Containment, Boilers
Journal Articles

Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique

Francesco Cordella, Mauro Cappelli, Massimo Sepielli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041003.
Paper No: NERS-15-1181
https://doi.org/10.1115/1.4033696
Published Online: October 12, 2016
View Article titled, Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique
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Topics: Algorithms, Boilers, Dynamics (Mechanics), Pressure, Sensors, Temperature, Transients (Dynamics), Water, Flow (Dynamics), Transmission lines