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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

Accepted Manuscript
Huiping Yan, Blair Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
Publisher: ASME
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: September 11, 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: Fuels, Hydrogen, Physics, Small modular reactors, Rods, Temperature, Coolants, Design, High temperature, Molten salt reactors
Journal Articles

On Frequency / Time Invariance of Certain Temporal and Complex Transfer Functions for the 1d Interfacial Monochromatic Neutron Density Wave

Accepted Manuscript
Nassar Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1061
https://doi.org/10.1115/1.4063291
Published Online: August 30, 2023
View Article titled, On Frequency / Time Invariance of Certain Temporal and Complex Transfer Functions for the 1d Interfacial Monochromatic Neutron Density Wave
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Topics: Density, Neutrons, Transfer functions, Waves, Diffusion (Physics), Optimization, Absorption, Cancer, Dynamics (Mechanics), Frequency response
Journal Articles

Experimental Study Of Helium Stratification In Multi-Compartment Containment Studies Facility

Accepted Manuscript
Bhuvaneshwar Gera, Pavan Sharma, Aditya Karanam, Shubham Mishra, Thangamani I, Nandan Saha, Anu Dutta, Priyanshu Goyal, Vishnu Verma, Jayanta Chattopadhyay
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1118
https://doi.org/10.1115/1.4063239
Published Online: August 24, 2023
View Article titled, Experimental Study Of Helium Stratification In Multi-Compartment Containment Studies Facility
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Topics: Containment, Helium, Hydrogen, Accidents, Geometry, Computational fluid dynamics, Domes (Structural elements), Nuclear reactors, Water
Journal Articles

“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”

Accepted Manuscript
Shu Jun Wang, Xianmin Huang, Yanfei Rao, Blair Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: August 24, 2023
View Article titled, “Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”
Open the PDF for “Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)” in another window
Topics: Pressurized water reactors, Small modular reactors, Testing, Thermal hydraulics, Flow (Dynamics), Oscillations, Boilers, Design, Circuits, Heat transfer
Journal Articles

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

Accepted Manuscript
Hakan Ozaltun, James I. Cole, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1048
https://doi.org/10.1115/1.4063163
Published Online: August 11, 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, Plates (structures), Thermomechanics, Stress, Aluminum alloys, Irradiation (Radiation exposure), Aluminum, Deformation, Engineering simulation
Journal Articles

Survey Analysis of Potential Nuclear Safety Research of Thailand for International Research Collaborative Reinforcement in the 2020s

Accepted Manuscript
Wasin Vechgama, Kampanart Silva
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1040
https://doi.org/10.1115/1.4063162
Published Online: August 11, 2023
View Article titled, Survey Analysis of Potential Nuclear Safety Research of Thailand for International Research Collaborative Reinforcement in the 2020s
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Topics: Safety, Nuclear power, Fukushima nuclear disaster, Japan, 2011, Risk assessment, Accidents, Disasters, Human factors, Nuclear research
Journal Articles

Depletion Calculations For An Integral Small Molten Salt Reactor With Serpent

Accepted Manuscript
Xiaolin Wang, T. Sinh Nguyen, Daniel T Wojtaszek
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1004
https://doi.org/10.1115/1.4063111
Published Online: August 5, 2023
View Article titled, Depletion Calculations For An Integral Small Molten Salt Reactor With Serpent
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Topics: Molten salt reactors, Fuels, Cycles, Flow (Dynamics), Simulation, Nuclear fission, Nuclear fuel cycle, Nuclear reactors, Separation (Technology), Spent nuclear fuels
Journal Articles

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

Accepted Manuscript
Yurong Li, Lixia He, Jing Wen, Jiewen Shao
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1027
https://doi.org/10.1115/1.4063039
Published Online: July 25, 2023
View Article titled, Study of γ-ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes
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Topics: Algorithms, Solid wastes, Steel, Algebra, Calibration, Damage, Simulation
Journal Articles

Total Loss of Feedwater Analysis of PWR Using RELAP5

Accepted Manuscript
Andrej Prošek
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1032
https://doi.org/10.1115/1.4063009
Published Online: July 21, 2023
View Article titled, Total Loss of Feedwater Analysis of PWR Using RELAP5
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Topics: Feedwater, Pressurized water reactors, Safety, Accidents, Design, Nuclear reactor coolants, Pumps, Boilers, Computers, Failure
Journal Articles

Implementation Of Solar Salt Properties Into Ariant And Simulation Of Pressurized Loss Of Forced Circulation In A High Temperature Gas-Cooled Small Modular Reactor

Accepted Manuscript
Jason Wu, Thomas Beuthe, Aleksandar Vasić
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1051
https://doi.org/10.1115/1.4062917
Published Online: July 7, 2023
View Article titled, Implementation Of Solar Salt Properties Into Ariant And Simulation Of Pressurized Loss Of Forced Circulation In A High Temperature Gas-Cooled Small Modular Reactor
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Topics: High temperature, Simulation, Small modular reactors, Solar energy, Coolants, Helium, Fluids, Heat storage, Licensing, Nuclear reactors
Journal Articles

Interactions Between Molten Sodium and Standard Pipe Insulation

Accepted Manuscript
Daniel LaBrier, Jordan Harley, Morgan Robbins
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1191
https://doi.org/10.1115/1.4062798
Published Online: June 20, 2023
View Article titled, Interactions Between Molten Sodium and Standard Pipe Insulation
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Topics: Pipe insulation, Sodium, Insulation, Leakage, Pipes, Heat, Binders (Materials), Design, Fire, Glass fiber insulation
Journal Articles

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

Accepted Manuscript
Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: June 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, Nuclear power stations, Containment, Ducts, Design, Exhaust systems, Failure, Fluids, Radiation measuring instruments, Radiation sources
Journal Articles

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

Accepted Manuscript
Sinisa Sadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgic
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: June 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Simulation, Uncertainty, Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Fuel rods, Safety, Steam, Acceptance criteria, Boundary-value problems
Journal Articles

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

Accepted Manuscript
Thomas Beuthe, Hooman Jazebizadeh, Aleksandar Vasic, Alex Pegarkov, Tarik Kaya, Hussam A M Zahlan
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1026
https://doi.org/10.1115/1.4062752
Published Online: June 16, 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: Cooling, Heat pipes, Potassium, Small modular reactors, Alkali metals, Computer simulation, Simulation models
Journal Articles

Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications

Accepted Manuscript
Abhishek Saraswat, Rajendraprasad Bhattacharyay, Paritosh Chaudhuri, Sateesh Gedupudi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1007
https://doi.org/10.1115/1.4062646
Published Online: May 27, 2023
View Article titled, Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications
Open the PDF for Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications in another window
Topics: Coatings, Flow (Dynamics), High temperature, Liquid metals, Manufacturing, Performance characterization, Insulation, Coolants, Corrosion, Fusion reactors
Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Accepted Manuscript
Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: July 15, 2022
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA
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Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations
Journal Articles

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Emmanuel O. Osigwe, Arnold Gad-Briggs, Dodeye Igbong, Theoklis Nikolaidis, Pericles Pilidis
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021201.
Paper No: NERS-19-1042
https://doi.org/10.1115/1.4044260
Published Online: February 24, 2020
View Article titled, Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy
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Topics: Cycles, Pressure, Stress, Temperature, Flow (Dynamics), Compressors, Power stations, Heat, Modeling, Closed-cycle gas turbines
Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.
Paper No: NERS-19-1024
https://doi.org/10.1115/1.4045035
Published Online: February 24, 2020
View Article titled, Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality
Journal Articles

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

Hai Quan Ho, Yuki Honda, Shimpei Hamamoto, Toshiaki Ishii, Shoji Takada, Nozomu Fujimoto, Etsuo Ishitsuka
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021902.
Paper No: NERS-19-1040
https://doi.org/10.1115/1.4044529
Published Online: February 24, 2020
View Article titled, Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor
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Topics: Irradiation (Radiation exposure), Neutrons, Silicon, Solar cells, High temperature, Particulate matter
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
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
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Topics: Blades, Coolants, Flow (Dynamics), Fuels, Neutrons, Supercritical water reactors, Thermal hydraulics, Transients (Dynamics), Water, Delays