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Journal Articles

Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014501.
Paper No: NERS-23-1015
https://doi.org/10.1115/1.4063007
Published Online: October 20, 2023
View Article titled, Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
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Topics: Computational fluid dynamics, Cooling systems, Flow (Dynamics), Fluid dynamics, Heat, Heavy water reactors, Inertia (Mechanics), Pressure, Temperature, Vessels
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

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

Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test

Huang Jingyu, Pan Xinxin, Song Chunjing
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031701.
Paper No: NERS-17-1198
https://doi.org/10.1115/1.4042495
Published Online: May 3, 2019
View Article titled, Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test
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Topics: Pressure, Wind, Wind tunnels, Wind velocity, Containment, Cooling systems, Pressurized water reactors, Air flow
Journal Articles

Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

Mukesh Kumar, P. K. Verma, A. K. Nayak, A. Rama Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041012.
Paper No: NERS-17-1007
https://doi.org/10.1115/1.4037031
Published Online: July 31, 2017
View Article titled, Experimental Demonstration of AHWR Safety During Prolonged Station Black Out
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Topics: Cooling systems, Design, Heat, Safety, Test facilities, Vessels, Water, Temperature, Fukushima nuclear disaster, Japan, 2011
Journal Articles

Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor

Yusuke Fujiwara, Takahiro Nemoto, Daisuke Tochio, Masanori Shinohara, Masato Ono, Shoji Takada
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041013.
Paper No: NERS-16-1123
https://doi.org/10.1115/1.4036985
Published Online: July 31, 2017
View Article titled, Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor
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Topics: Cooling, Cooling systems, Temperature, Vessels, Water, Concretes, High temperature, Heat, Helium, Coolants
Journal Articles

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041009.
Paper No: NERS-17-1021
https://doi.org/10.1115/1.4037188
Published Online: July 31, 2017
View Article titled, Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0
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Topics: Accidents, Coolants, Flow (Dynamics), Vessels, Temperature, Heat, Pressure, Cooling systems, Water, Tungsten
Journal Articles

Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System

Tianji Peng, Zhiwei Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2017, 3(2): 024502.
Paper No: NERS-16-1037
https://doi.org/10.1115/1.4035333
Published Online: March 1, 2017
View Article titled, Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System
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Topics: Heat, Heat transfer, Helium, Transients (Dynamics), Cooling systems, Mathematics, Fluids
Journal Articles

Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014503.
Paper No: NERS-16-1012
https://doi.org/10.1115/1.4034680
Published Online: December 20, 2016
View Article titled, Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code
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Topics: Accidents, Coolants, Flow (Dynamics), Heat, Helium, Vessels, Safety, Cooling systems, Design, Temperature
Journal Articles

Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating

Masato Ono, Atsushi Shimizu, Makoto Kondo, Yosuke Shimazaki, Masanori Shinohara, Daisuke Tochio, Kazuhiko Iigaki, Shigeaki Nakagawa, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044502.
Paper No: NERS-15-1178
https://doi.org/10.1115/1.4032478
Published Online: October 12, 2016
View Article titled, Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating
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Topics: Cooling, Heating, Temperature, Water, Cooling systems, Vessels, Flow (Dynamics), Heat