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Journal Articles

Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

Available to Purchase
Andy Rivas, Gregory K. Delipei, Jason Hou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021801.
Paper No: NERS-24-1017
https://doi.org/10.1115/1.4066777
Published Online: December 5, 2024
View Articletitled, Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
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Topics: Electricity (Physics), Optimization, Probability, Maintenance, Steam, Safety, Temperature, Pumps, Uncertainty, Turbines
Journal Articles

Investigation of Metal–H 2 O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions

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Olga Y. Palazhchenko, Matthew H. Kaye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021601.
Paper No: NERS-23-1110
https://doi.org/10.1115/1.4066339
Published Online: September 30, 2024
View Articletitled, Investigation of Metal–H 2 O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions
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Topics: Equilibrium (Physics), Metals, Temperature, Vessels, Water, Instrumentation
Journal Articles

Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects

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Victor Richet, Sarah Piochaud, Mouna El Alaoui, Robert Plana
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012202.
Paper No: NERS-23-1059
https://doi.org/10.1115/1.4064466
Published Online: May 10, 2024
View Articletitled, Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects
Open the PDF for Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects in another window
Topics: Modeling, Teams, Knowledge management, Workflow, Systems engineering, Design, Engineering disciplines
Journal Articles

Greetings From the Chair of the JSME Power Energy Systems Division

Free
Takashi Kiga
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2024, 10(1): 010302.
Paper No: NERS-23-1107
https://doi.org/10.1115/1.4063882
Published Online: December 8, 2023
View Articletitled, Greetings From the Chair of the JSME Power Energy Systems Division
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Topics: Energy / power systems, Japan Society of Mechanical Engineers
Journal Articles

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

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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 Articletitled, 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

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

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Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
Paper No: NERS-21-1160
https://doi.org/10.1115/1.4055328
Published Online: December 14, 2022
View Articletitled, Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
Open the PDF for Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors in another window
Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants
Journal Articles

Greetings from the Chair of the JSME Power Energy Systems Division

Free
Hitoshi Asano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2023, 9(1): 010302.
Paper No: NERS-22-1134
https://doi.org/10.1115/1.4056050
Published Online: December 2, 2022
View Articletitled, Greetings from the Chair of the JSME Power Energy Systems Division
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Topics: Energy / power systems, Japan Society of Mechanical Engineers, Nuclear engineering
Journal Articles

Greetings From the Chair of the JSME Power Energy Systems Division (PESD)

Free
Hisatsune Masakazu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2022, 8(1): 010302.
Paper No: NERS-21-1127
https://doi.org/10.1115/1.4052666
Published Online: December 14, 2021
View Articletitled, Greetings From the Chair of the JSME Power Energy Systems Division (PESD)
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Topics: Energy / power systems, Japan Society of Mechanical Engineers
Journal Articles

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

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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 Articletitled, 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

Proactive Human Error Reduction Using the Systems Engineering Process

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Jonathan K. Corrado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024502.
Paper No: NERS-20-1015
https://doi.org/10.1115/1.4051362
Published Online: October 19, 2021
View Articletitled, Proactive Human Error Reduction Using the Systems Engineering Process
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Topics: Design, Errors, Systems engineering
Journal Articles

Molecular Dynamics of Supercritical Water for Nuclear Data Development

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Katy Hartling, Gang Li, Ghaouti Bentoumi, Zahra Yamani
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021301.
Paper No: NERS-20-1179
https://doi.org/10.1115/1.4051790
Published Online: October 19, 2021
View Articletitled, Molecular Dynamics of Supercritical Water for Nuclear Data Development
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Topics: Molecular dynamics simulation, Simulation, Statistical process control, Water, Electromagnetic scattering, Radiation scattering, Scattering (Physics)
Journal Articles

Superphénix Benchmark Part II: Transient Results

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A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011321.
Paper No: NERS-21-1052
https://doi.org/10.1115/1.4051877
Published Online: October 8, 2021
View Articletitled, Superphénix Benchmark Part II: Transient Results
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Topics: Flow (Dynamics), Fuels, Sodium, Temperature, Transients (Dynamics), Modeling
Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

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Alexander Ponomarev, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.
Paper No: NERS-20-1186
https://doi.org/10.1115/1.4051514
Published Online: September 13, 2021
View Articletitled, Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor
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Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat
Journal Articles

Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models

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Gustavo D. Pereira, Jian Su
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041604.
Paper No: NERS-20-1104
https://doi.org/10.1115/1.4049196
Published Online: August 20, 2021
View Articletitled, Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models
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Topics: Fuels, Heat, Slabs, Temperature, Temperature profiles, Pressurized water reactors, Systems analysis, Fuel rods
Journal Articles

Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities

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Kalpesh Joshi, Bikash Poudel, Ramakrishna (Rama) Gokaraju
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031303.
Paper No: NERS-20-1051
https://doi.org/10.1115/1.4048896
Published Online: March 16, 2021
View Articletitled, Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities
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Topics: Design, Nuclear power stations, Simulation, Small modular reactors, Stress, Turbines, Power systems (Machinery), Governors, Steady state, Flow (Dynamics)
Journal Articles

The Intersection of Advancing Technology and Human Performance

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Jonathan K. Corrado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010801.
Paper No: NERS-19-1109
https://doi.org/10.1115/1.4047717
Published Online: October 2, 2020
View Articletitled, The Intersection of Advancing Technology and Human Performance
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Topics: Errors, Machinery, Human factors, Design
Journal Articles

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

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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 Articletitled, 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

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

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Mithil Parekh, Yuan Gao, Mariana Jockenhoevel-Barttfeld, Karl Waedt
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031802.
Paper No: NERS-17-1277
https://doi.org/10.1115/1.4046262
Published Online: May 5, 2020
View Articletitled, Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems
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Topics: Computer software, Failure, Instrumentation, Modeling, Nuclear power stations, Safety, Control systems, Hardware, Three-dimensional modeling
Journal Articles

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

Open Access
M. D. Tucker, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401.
Paper No: NERS-19-1065
https://doi.org/10.1115/1.4045485
Published Online: March 9, 2020
View Articletitled, The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors
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Topics: Algorithms, Cross section (Physics), Feedback, Fuels, Simulation, Uncertainty, Uncertainty analysis, Uranium, Physics, Diffusion (Physics)
Journal Articles

Estimation of Flow-Accelerated Corrosion Rate in Nuclear Piping System

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Indranil Hazra, Mahesh D. Pandey, Mikko I. Jyrkama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011106.
Paper No: NERS-19-1032
https://doi.org/10.1115/1.4044407
Published Online: November 25, 2019
View Articletitled, Estimation of Flow-Accelerated Corrosion Rate in Nuclear Piping System
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Topics: Algorithms, Chain, Computation, Corrosion, Density, Flow (Dynamics), Parameter estimation, Pipes, Piping systems, Wall thickness