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Journal Articles

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

Yue Zou, Brian Derreberry

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.

Paper No: NERS-21-1040

DOI: https://doi.org/10.1115/1.4053013

Published Online: May 26, 2022

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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification

Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.

Paper No: NERS-20-1206

DOI: https://doi.org/10.1115/1.4053689

Published Online: May 26, 2022

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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations

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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 042301.

Paper No: NERS-21-1025

DOI: https://doi.org/10.1115/1.4050768

Published Online: March 16, 2022

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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

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

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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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.

Paper No: NERS-20-1207

DOI: https://doi.org/10.1115/1.4051612

Published Online: October 19, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011317.

Paper No: NERS-20-1066

DOI: https://doi.org/10.1115/1.4052376

Published Online: October 4, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.

Paper No: NERS-20-1204

DOI: https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.

Paper No: NERS-20-1080

DOI: https://doi.org/10.1115/1.4051723

Published Online: August 12, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032004.

Paper No: NERS-20-1107

DOI: https://doi.org/10.1115/1.4049345

Published Online: April 16, 2021

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Topics: Waves, Pipes, Signals, Cylinders

Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.

Paper No: NERS-20-1012

DOI: https://doi.org/10.1115/1.4048477

Published Online: March 16, 2021

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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors

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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031602.

Paper No: NERS-20-1052

DOI: https://doi.org/10.1115/1.4049096

Published Online: March 16, 2021

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Topics: Gallium, Metals, Pipes, Solidification, Temperature, Computer simulation, Reynolds number, Flow (Dynamics), Wall temperature

Journal Articles

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

J. Patera, J. Jansa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021803.

Paper No: NERS-20-1108

DOI: https://doi.org/10.1115/1.4048238

Published Online: November 16, 2020

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702.

Paper No: NERS-19-1131

DOI: https://doi.org/10.1115/1.4046257

Published Online: October 1, 2020

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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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.

Paper No: NERS-19-1168

DOI: https://doi.org/10.1115/1.4047441

Published Online: September 4, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.

Paper No: NERS-19-1082

DOI: https://doi.org/10.1115/1.4046783

Published Online: June 5, 2020

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021202.

Paper No: NERS-19-1039

DOI: https://doi.org/10.1115/1.4045121

Published Online: February 24, 2020

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021110.

Paper No: NERS-19-1072

DOI: https://doi.org/10.1115/1.4046296

Published Online: February 24, 2020

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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

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

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Topics: Flow (Dynamics), Fluids, Heat exchangers, Heat transfer, Modeling, Simulation, Temperature, Transients (Dynamics), Turbulence, Computational fluid dynamics

Journal Articles

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401.

Paper No: NERS-17-1237

DOI: https://doi.org/10.1115/1.4045125

Published Online: November 29, 2019

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Topics: Evaporation, Flow (Dynamics), High temperature, Leakage, Pipes, Pressure, Sensors, Sprays, Temperature, Temperature distribution

Journal Articles

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

Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.

Paper No: NERS-19-1001

DOI: https://doi.org/10.1115/1.4044847

Published Online: November 29, 2019

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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models

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Journal citation

NARROW

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

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

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

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

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

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

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

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

Guided Waves Measurement Techniques in Pitch–Catch Configuration

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

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

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

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

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

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

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

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

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

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

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

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