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Journal Articles

Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant

Ryota Miyake, Shinya Tominaga, Yusuke Terakado, Naoyuki Takado, Toshio Aoki, Chikashi Miyamoto, Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kota Nakata
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2025, 11(1): 011701.
Paper No: NERS-23-1062
https://doi.org/10.1115/1.4064123
Published Online: May 10, 2024
View Article titled, Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant
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Topics: Artificial intelligence, Nuclear power stations, Power stations, Pumps, Fluctuations (Physics), Signals, Feedwater, Linkages, Time series, Transients (Dynamics)
Journal Articles

Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions

Yuqi Liu, Minghui Chen, Shuai Che, Adam Burak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030908.
Paper No: NERS-23-1084
https://doi.org/10.1115/1.4064336
Published Online: March 8, 2024
View Article titled, Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions
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Topics: Bearings, Journal bearings, Lubrication, Pumps, Damping, Stiffness, High temperature
Journal Articles

Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5

Andrej Prošek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011401.
Paper No: NERS-23-1032
https://doi.org/10.1115/1.4063009
Published Online: October 20, 2023
View Article titled, Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5
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Topics: Design, Feedwater, Pressurized water reactors, Pumps, Safety, Accidents, Nuclear reactor coolants
Journal Articles

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.
Paper No: NERS-20-1167
https://doi.org/10.1115/1.4052591
Published Online: January 11, 2022
View Article titled, On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix
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Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps
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

Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability

Boris Haranki, Ufuk Dilek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024501.
Paper No: NERS-19-1159
https://doi.org/10.1115/1.4051363
Published Online: October 19, 2021
View Article titled, Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability
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Topics: ASTM International, Concretes, Design, Flow (Dynamics), Nuclear construction, Pumps, Stability
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, 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): 011311.
Paper No: NERS-20-1059
https://doi.org/10.1115/1.4051364
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design
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Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water
Journal Articles

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

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 Article titled, 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

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

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.
Paper No: NERS-20-1157
https://doi.org/10.1115/1.4050207
Published Online: March 10, 2021
View Article titled, Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario
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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors
Journal Articles

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Terry Price, Zack Taylor, Ondrej Chvala
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041302.
Paper No: NERS-19-1107
https://doi.org/10.1115/1.4046258
Published Online: June 3, 2020
View Article titled, A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors
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Topics: Bubbles, Fuels, Molten salt reactors, Porosity, Pressure, Nuclear fission, Flow (Dynamics), Pumps
Journal Articles

Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

Edward Shitsi, Emmanuel K. Boafo, Felix Ameyaw, H. C. Odoi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031801.
Paper No: NERS-19-1117
https://doi.org/10.1115/1.4045803
Published Online: March 9, 2020
View Article titled, Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method
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Topics: Failure, Feedwater, High pressure (Physics), Pumps, Safety, Valves, Nuclear power stations
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

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

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 Article titled, 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

Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

S. P. Saraswat, D. Ray, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 042202.
Paper No: NERS-18-1030
https://doi.org/10.1115/1.4042707
Published Online: July 19, 2019
View Article titled, Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0
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Topics: Accidents, Coolants, Cooling systems, Design, Heat, Heat sinks, Modeling, Plasmas (Ionized gases), Pressure, Sprays
Journal Articles

The Necessity to Reexamine Key Component Material With Spectrometry Analysis in the Nuclear Island

Chongzhi Wu, Jindong Zhang, Zongkui Wang, Zengkui Zhang, Shenqing Fu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Discussions
ASME J of Nuclear Rad Sci. April 2019, 5(2): 025501.
Paper No: NERS-17-1172
https://doi.org/10.1115/1.4042221
Published Online: March 15, 2019
View Article titled, The Necessity to Reexamine Key Component Material With Spectrometry Analysis in the Nuclear Island
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Topics: Metals, Nuclear power, Spectroscopy, Welding, Pumps, Nozzles, Construction, Pipes, Heat
Journal Articles

Precautions at Fukushima That Would Have Suppressed the Accident Severity

Kenji Iino, Ritsuo Yoshioka, Masao Fuchigami, Masayuki Nakao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031007.
Paper No: NERS-17-1051
https://doi.org/10.1115/1.4039343
Published Online: May 16, 2018
View Article titled, Precautions at Fukushima That Would Have Suppressed the Accident Severity
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Topics: Accidents, Earthquakes, Fukushima nuclear disaster, Japan, 2011, Seawater, Tsunamis, Water, Heat, Pumps, Electricity (Physics), Evaporation
Journal Articles

Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

Gueorgui I. Petkov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020905.
Paper No: NERS-16-1133
https://doi.org/10.1115/1.4039000
Published Online: March 5, 2018
View Article titled, Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events
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Topics: Accidents, Design, Errors, Safety, Scram, Transients (Dynamics), Water, Pressure, Delays, Valves
Journal Articles

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Rafael Bocanegra, Valentino Di Marcello, Victor H. Sánchez-Espinoza, Gonzalo Jiménez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020908.
Paper No: NERS-16-1114
https://doi.org/10.1115/1.4038062
Published Online: March 5, 2018
View Article titled, Fukushima Unit 2 Accident Simulation With MELCOR 2.1
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Topics: Accidents, Containment, Fukushima nuclear disaster, Japan, 2011, Pressure, Safety, Simulation, Underground injection, Leakage, Pumps, Flow (Dynamics)
Journal Articles

Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load

Emiliya Georgieva, Yavor Dinkov, Kostadin Ivanov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031005.
Paper No: NERS-16-1132
https://doi.org/10.1115/1.4035550
Published Online: May 25, 2017
View Article titled, Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load
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Topics: Coolants, Flow (Dynamics), Fuels, Manufacturing, Pressure, Simulation, Steam, Stress, Temperature, Transients (Dynamics)