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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

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Article titled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
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Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
Journal Articles

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
Paper No: NERS-22-1119
https://doi.org/10.1115/1.4056930
Published Online: March 13, 2023
View Article titled, Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
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Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
Paper No: NERS-22-1165
https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Article titled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
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Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
https://doi.org/10.1115/1.4056463
Published Online: February 8, 2023
View Article titled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
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Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods
Journal Articles

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Design Innovation Paper
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
Paper No: NERS-21-1157
https://doi.org/10.1115/1.4054726
Published Online: June 15, 2022
View Article titled, ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
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Topics: Design, Optimization, Safety, Thermal hydraulics, Nuclear design, Nuclear reactors, Computer simulation
Journal Articles

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

Alain Flores y Flores, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201.
Paper No: NERS-20-1034
https://doi.org/10.1115/1.4048006
Published Online: May 27, 2022
View Article titled, Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
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Topics: Explosions, Hydrogen, Aerosols, Thermal hydraulics, Pressure, Flames, Test facilities
Journal Articles

Dr. Romney B. Duffey on His 80th Birthday

Igor Pioro, Richard R. Schultz, Dr. Hideki Kamide, Dr. Sama Bilbao y Leon, Dr. Nils Diaz, Alexander V. Bychkov, Dr. Leon Cizelj, Francesco D'Auria, Dr. Yanping Huang, Dr. Yasuo Koizumi, Tomio Okawa, Dr. Robert Walker, Dr. Robert Youngblood, Enrico Zio
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. July 2022, 8(3): 030201.
Paper No: NERS-22-1030
https://doi.org/10.1115/1.4054329
Published Online: May 3, 2022
View Article titled, Dr. Romney B. Duffey on His 80th Birthday
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Topics: Accidents, Design, Electricity (Physics), Governments, Innovation, Japan Society of Mechanical Engineers, Nuclear engineering, Nuclear power, Risk, Safety
Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.
Paper No: NERS-21-1036
https://doi.org/10.1115/1.4050770
Published Online: October 19, 2021
View Article titled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark
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Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation
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

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.
Paper No: NERS-20-1208
https://doi.org/10.1115/1.4049854
Published Online: February 26, 2021
View Article titled, Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
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Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design
Journal Articles

European Research Program on Supercritical Water-Cooled Reactor

M. Kryková, T. Schulenberg, M. Arnoult Růžičková, A. Sáez-Maderuelo, I. Otic, S. Czifrus, L. Cizelj, G. L. Pavel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021301.
Paper No: NERS-20-1090
https://doi.org/10.1115/1.4048901
Published Online: November 16, 2020
View Article titled, European Research Program on Supercritical Water-Cooled Reactor
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Topics: Design, Safety, Small modular reactors, Supercritical water reactors, Water, Corrosion, Thermal hydraulics, Physics
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Article titled, A Simplified Two-Group Multipoint Kinetics Model
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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics
Journal Articles

Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

Lianjie Wang, Lei Yao, Ping Yang, Di Lu, Wenbo Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031103.
Paper No: NERS-19-1054
https://doi.org/10.1115/1.4044408
Published Online: June 5, 2020
View Article titled, Study on Calculation Difference of the SCWR Core Steady-State Analysis Code
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Topics: Density, Feedback, Steady state, Supercritical water reactors, Thermal hydraulics, Water, Flow (Dynamics)
Journal Articles

Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”

Vivek A. Kale, Obaidurrahman K.
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031501.
Paper No: NERS-19-1074
https://doi.org/10.1115/1.4045394
Published Online: March 9, 2020
View Article titled, Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”
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Topics: Coolants, Fuels, Neutrons, Simulation, Temperature, Transients (Dynamics), Dynamics (Mechanics), Thermal hydraulics
Journal Articles

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

David William Hummel, David Raymond Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041403.
Paper No: NERS-18-1008
https://doi.org/10.1115/1.4042597
Published Online: September 3, 2019
View Article titled, Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics
Open the PDF for Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics in another window
Topics: Blades, Coolants, Flow (Dynamics), Fuels, Neutrons, Supercritical water reactors, Thermal hydraulics, Transients (Dynamics), Water, Delays
Journal Articles

Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka, Hiroyuki Ohshima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021001.
Paper No: NERS-17-1280
https://doi.org/10.1115/1.4042191
Published Online: March 15, 2019
View Article titled, Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor
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Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium, Temperature distribution, Temperature, Sodium fast reactors, Wire, Thermal hydraulics
Journal Articles

Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients

Wang Lianjie, Lu Di, Zhao Wenbo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011010.
Paper No: NERS-18-1047
https://doi.org/10.1115/1.4041693
Published Online: January 24, 2019
View Article titled, Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients
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Topics: Safety, Supercritical water reactors, Thermal hydraulics, Transient analysis, Transients (Dynamics), Accidents, Fuels, Temperature, Water, Density
Journal Articles

Special Issue: Special Edition ICONE-25

Robert Stakenborghs
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. October 2018, 4(4): 040301.
Paper No: NERS-18-1052
https://doi.org/10.1115/1.4040963
Published Online: September 10, 2018
View Article titled, Special Issue: Special Edition ICONE-25
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Topics: China, Japan Society of Mechanical Engineers, Nuclear engineering, Nuclear power, Students, Mechanical engineers, Accidents, Computational fluid dynamics, Construction, Cycles
Journal Articles

Parallel Analysis of Linear Systems in CORTH and KYLIN2

Pingzhou Ming, Dingyong Chen, Bin Wu, Wei Lu, Dong Liu, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031010.
Paper No: NERS-17-1143
https://doi.org/10.1115/1.4039036
Published Online: May 16, 2018
View Article titled, Parallel Analysis of Linear Systems in CORTH and KYLIN2
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Topics: Linear systems, Thermal hydraulics, Manufacturing, Cores (Molding materials)