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Journal Articles

Special Experimental Environment for Gen. IV Reactors with Graphite Reflector

Accepted Manuscript
Eva Vilimová, Tomáš Peltan, Radek Škoda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1017
https://doi.org/10.1115/1.4064124
Published Online: November 23, 2023
View Article titled, Special Experimental Environment for Gen. IV Reactors with Graphite Reflector
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Topics: Graphite, Neutrons, Nuclear reactors, Design, Instrumentation, Neutron flux, Optical mirrors, Small modular reactors
Journal Articles

Development of an Ai-Based Predictive Anomaly Detection System to Nuclear Power Plant

Accepted Manuscript
Ryota Miyake, Shinya Tominaga, Yusuke Terakado, Naoyuki Takado, Toshio Aoki, Chikashi Miyamoto, Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kota Nakata
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1062
https://doi.org/10.1115/1.4064123
Published Online: November 23, 2023
View Article titled, Development of an Ai-Based Predictive Anomaly Detection System to Nuclear Power Plant
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Topics: Nuclear power stations, Algorithms, Artificial neural networks, Signals, Time series, Transients (Dynamics)
Journal Articles

Influence of Non-Condensable Gas-Dust Mixture On Direct Contact Condensation of Steam At Atmospheric Pressure

Accepted Manuscript
Luca Berti, Alessio Pesetti, Michele Raucci, Guglielmo Giambartolomei, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1020
https://doi.org/10.1115/1.4064066
Published Online: November 18, 2023
View Article titled, Influence of Non-Condensable Gas-Dust Mixture On Direct Contact Condensation of Steam At Atmospheric Pressure
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Topics: Atmospheric pressure, Condensation, Dust, Steam, Water, Fluids, Heat transfer coefficients, Pressure, Temperature, Vacuum
Journal Articles

Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations

Thomas Beuthe, Hooman Jazebizadeh, Aleksandar Vasić, Alex Pegarkov, Tarik Kaya, Hussam Zahlan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021401.
Paper No: NERS-22-1026
https://doi.org/10.1115/1.4062752
Published Online: November 1, 2023
View Article titled, Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations
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Topics: Potassium, Temperature, Vapors, Heat pipes
Includes: Supplementary data
Journal Articles

Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding

Hakan Ozaltun, James I. Cole, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021601.
Paper No: NERS-23-1048
https://doi.org/10.1115/1.4063163
Published Online: November 1, 2023
View Article titled, Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Irradiation (Radiation exposure), Plates (structures), Deformation
Journal Articles

Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories

R. David, B. Mitchell, J. H. Spencer, N. Lair, S. M. Petoukhov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2024, 10(2): 024501.
Paper No: NERS-23-1049
https://doi.org/10.1115/1.4063673
Published Online: November 1, 2023
View Article titled, Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories
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Topics: Accidents, Zirconium, Electromagnetic induction
Journal Articles

Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

Huiping V. Yan, 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): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 2023
View Article titled, Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
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Topics: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics
Journal Articles

Greetings From the Chair of the Jsme Power Energy Systems Division

Accepted Manuscript
Takashi Kiga
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1107
https://doi.org/10.1115/1.4063882
Published Online: October 21, 2023
View Article titled, 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, Radiation (Physics)
Journal Articles

Application of Level 3 Probabilistic Safety Analysis In UK HPR1000

Accepted Manuscript
Jinkai Wang, Qi Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1112
https://doi.org/10.1115/1.4063874
Published Online: October 21, 2023
View Article titled, Application of Level 3 Probabilistic Safety Analysis In UK HPR1000
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Topics: Probabilistic safety assessment, Accidents, Design, Nuclear power stations, Radiation (Physics), Radiation sources, Risk
Journal Articles

Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko

Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011701.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: October 20, 2023
View Article titled, Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
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Topics: Accidents, Containment, Ducts, Nuclear power stations, Fluids
Journal Articles

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
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

Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5

Andrej Prošek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011401.
Paper No: NERS-23-1032
https://doi.org/10.1115/1.4063009
Published Online: October 20, 2023
View Article titled, Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5
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Topics: Design, Feedwater, Pressurized water reactors, Pumps, Safety, Accidents, Nuclear reactor coolants
Journal Articles

Study of γ-Ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes

Yurong Li, Lixia He, Jing Wen, Jiewen Shao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 012001.
Paper No: NERS-23-1027
https://doi.org/10.1115/1.4063039
Published Online: October 20, 2023
View Article titled, Study of γ-Ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes
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Topics: Algebra, Algorithms, Sensors, Simulation, Solid wastes, Steel, Radioactive wastes, Computerized tomography
Journal Articles

Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations

Thomas Beuthe, Aleksandar Vasić, Chukwudi Azih, Pablo D. G. Maqueo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. April 2024, 10(2): 020801.
Paper No: NERS-23-1052
https://doi.org/10.1115/1.4063112
Published Online: October 20, 2023
View Article titled, Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations
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Topics: Sodium, Temperature, Vapors, Heat pipes
Includes: Supplementary data
Journal Articles

Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent

Xiaolin Wang, T. Sinh Nguyen, Daniel Wojtaszek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021301.
Paper No: NERS-23-1004
https://doi.org/10.1115/1.4063111
Published Online: October 20, 2023
View Article titled, Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent
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Topics: Fuels, Molten salt reactors, Flow (Dynamics), Cycles, Nuclear fission
Journal Articles

Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility

Bhuvaneshwar Gera, Pavan K. Sharma, Aditya Karanam, Shubham Mishra, I. Thangamani, Nandan Saha, Anu Dutta, Priyanshu Goyal, Vishnu Verma, Jayanta Chattopadhyay
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021701.
Paper No: NERS-22-1118
https://doi.org/10.1115/1.4063239
Published Online: October 20, 2023
View Article titled, Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility
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Topics: Containment, Errors, Helium, Hydrogen
Journal Articles

On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave

Nassar H. S. Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021501.
Paper No: NERS-23-1061
https://doi.org/10.1115/1.4063291
Published Online: October 20, 2023
View Article titled, On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave
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Topics: Density, Neutrons, Transfer functions, Waves
Journal Articles

Advancement toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique

Satya Prakash Saraswat, Nicola Forgione, Massimo Emilio Angiolini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021302.
Paper No: NERS-23-1045
https://doi.org/10.1115/1.4063572
Published Online: October 20, 2023
View Article titled, Advancement toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique
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Topics: Calibration, Differential scanning calorimetry, Heating, Latent heat, Melting, Melting point, Specific heat, Temperature, Thermal properties, Uncertainty
Journal Articles

Technical Evaluation Requirements on Welding-Related Nonconformance Reports

Chongzhi Wu, Mingkai Li, Zongkui Wang, Zhenguo Peng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 022101.
Paper No: NERS-23-1035
https://doi.org/10.1115/1.4063630
Published Online: October 20, 2023
View Article titled, Technical Evaluation Requirements on Welding-Related Nonconformance Reports
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Topics: Welding, Construction, Design