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Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041802.
Paper No: NERS-23-1050
https://doi.org/10.1115/1.4062865
Published Online: September 15, 2023
View Article titled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation
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Topics: Errors, Flow (Dynamics), Instrumentation, Measurement uncertainty, Uncertainty, Nuclear power stations, Sensors, Pipes
Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.
Paper No: NERS-20-1206
https://doi.org/10.1115/1.4053689
Published Online: May 26, 2022
View Article titled, Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations
Journal Articles

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Yue Zou, Brian Derreberry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.
Paper No: NERS-21-1040
https://doi.org/10.1115/1.4053013
Published Online: May 26, 2022
View Article titled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities
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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification
Journal Articles

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

Miriam Ibba, Alessio Pesetti, Michele Raucci, Flavio Parozzi, Roberta Lazzeri, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 042301.
Paper No: NERS-21-1025
https://doi.org/10.1115/1.4050768
Published Online: March 16, 2022
View Article titled, Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses
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Topics: Dust, Water, Containers, Vessels, Pipes
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

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
https://doi.org/10.1115/1.4051612
Published Online: October 19, 2021
View Article titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature
Journal Articles

Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Hubert Delacroix, Frédéric Navacchia
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011317.
Paper No: NERS-20-1066
https://doi.org/10.1115/1.4052376
Published Online: October 4, 2021
View Article titled, Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing
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Topics: Evacuations, Flow (Dynamics), Flowmeters, Jets, Pipes, Sodium, Eddies (Fluid dynamics), Eddy currents (Electricity), Geometry, Design
Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, 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): 011314.
Paper No: NERS-20-1204
https://doi.org/10.1115/1.4051292
Published Online: September 20, 2021
View Article titled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety
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

Guided Waves Measurement Techniques in Pitch–Catch Configuration

Francesco Cordella, Francesco Bertoncini, Mauro Cappelli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 032004.
Paper No: NERS-20-1107
https://doi.org/10.1115/1.4049345
Published Online: April 16, 2021
View Article titled, Guided Waves Measurement Techniques in Pitch–Catch Configuration
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Topics: Waves, Pipes, Signals, Cylinders
Journal Articles

Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow

Shawn Somers-Neal, Alex Pegarkov, Edgar Matida, Vinh Tang, Tarik Kaya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031602.
Paper No: NERS-20-1052
https://doi.org/10.1115/1.4049096
Published Online: March 16, 2021
View Article titled, Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow
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Topics: Gallium, Metals, Pipes, Solidification, Temperature, Computer simulation, Reynolds number, Flow (Dynamics), Wall temperature
Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.
Paper No: NERS-20-1012
https://doi.org/10.1115/1.4048477
Published Online: March 16, 2021
View Article titled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors
Journal Articles

Application of Nonlinear Elastic Wave Spectroscopy in the Field of Nuclear Energy

J. Patera, J. Jansa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021803.
Paper No: NERS-20-1108
https://doi.org/10.1115/1.4048238
Published Online: November 16, 2020
View Article titled, Application of Nonlinear Elastic Wave Spectroscopy in the Field of Nuclear Energy
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Topics: Elastic waves, Excitation, Nuclear power, Spectroscopy, Concretes, Microcracks, Pipes, Steel, Concrete beams, Concrete testing
Journal Articles

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702.
Paper No: NERS-19-1131
https://doi.org/10.1115/1.4046257
Published Online: October 1, 2020
View Article titled, Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe
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Topics: Pipes, Temperature, Vessels, Heavy water reactors
Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.
Paper No: NERS-19-1168
https://doi.org/10.1115/1.4047441
Published Online: September 4, 2020
View Article titled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
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Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves
Journal Articles

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

A. Nava-Dominguez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.
Paper No: NERS-19-1082
https://doi.org/10.1115/1.4046783
Published Online: June 5, 2020
View Article titled, Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR
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Topics: Flow (Dynamics), Friction, Pressure drop, Wire, Fuels, Water, Supercritical water reactors, Manufacturing, Pipes
Journal Articles

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

Damian E. Ramajo, Santiago F. Corzo, Norberto M. Nigro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021202.
Paper No: NERS-19-1039
https://doi.org/10.1115/1.4045121
Published Online: February 24, 2020
View Article titled, Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors
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Topics: Flow (Dynamics), Fluids, Pipes, Pressure, Simulation, Water, Computational fluid dynamics, Geometry, Drainage, Computer simulation
Journal Articles

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Michele Andreani, Ralf Kapulla, Stephan Kelm, Domenico Paladino, Sidharth Paranjape
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021110.
Paper No: NERS-19-1072
https://doi.org/10.1115/1.4046296
Published Online: February 24, 2020
View Article titled, Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code
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Topics: Elevations (Drawings), Erosion, Flow (Dynamics), Helium, Pipes, Simulation, Steam, Temperature, Turbulence, Vessels
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
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 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

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