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Journal Articles

Comparative Maps of Safety Features for Fission and Fusion Reactors

Tu Nguyen, Eann A. Patterson, Richard J. Taylor, Y. S. Tseng, Chris Waldon
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
Publisher: ASME
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041701.
Paper No: NERS-22-1045
https://doi.org/10.1115/1.4062643
Published Online: September 15, 2023
View Article titled, Comparative Maps of Safety Features for Fission and Fusion Reactors
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Topics: Fusion reactors, Nuclear fission, Safety, Hazards
Journal Articles

Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production

Lekhnath Ghimire, Edward Waller
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
Publisher: ASME
ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501.
Paper No: NERS-23-1006
https://doi.org/10.1115/1.4062644
Published Online: September 15, 2023
View Article titled, Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production
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Topics: Design, Safety, Small modular reactors, Fuels
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

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

Development Of Analysis Tools For Heat Pipes Used In Small Modular Reactors: Sodium Property Correlations

Accepted Manuscript
Thomas Beuthe, Aleksandar Vasić, Chukwudi Azih, Pablo Diazgomezmaqueo
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Review Articles
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1052
https://doi.org/10.1115/1.4063112
Published Online: August 5, 2023
View Article titled, Development Of Analysis Tools For Heat Pipes Used In Small Modular Reactors: Sodium Property Correlations
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Topics: Heat pipes, Small modular reactors, Sodium, Design, Safety, Alkali metals, Fluids, Heat, Licensing, Modeling
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

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
Publisher: ASME
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107.
Paper No: NERS-22-1162
https://doi.org/10.1115/1.4062879
Published Online: July 17, 2023
View Article titled, A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
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Topics: Molten salt reactors, Simulation, Wall thickness, Safety, Computer simulation, Design, Temperature, Heat conduction, Melting, Solidification
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

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.
Paper No: NERS-22-1020
https://doi.org/10.1115/1.4056239
Published Online: February 8, 2023
View Article titled, Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
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Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection
Journal Articles

Machine Learning Metamodel of a Computationally Intense LOCA Code

Landon A. Conner, Clarence L. Worrell, Jun Liao, James P. Spring, Reza A. Karimi, Jeremy S. Marquardt, Joseph D. Wieder
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031402.
Paper No: NERS-22-1002
https://doi.org/10.1115/1.4056465
Published Online: February 8, 2023
View Article titled, Machine Learning Metamodel of a Computationally Intense LOCA Code
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Topics: Artificial neural networks, Genetic algorithms, Machine learning, Safety, Pressurized water reactors
Journal Articles

Editorial

Igor L. Pioro
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Editorial
ASME J of Nuclear Rad Sci. January 2023, 9(1): 010201.
Paper No: NERS-22-1120
https://doi.org/10.1115/1.4056024
Published Online: December 2, 2022
View Article titled, Editorial
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Topics: China, Nuclear engineering, Nuclear reactors, Radiation (Physics), Safety, Statistics
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
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

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

Chongzhi Wu, Haoming Sun, Zhenguo Peng, Benzheng Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Expert View
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014701.
Paper No: NERS-21-1177
https://doi.org/10.1115/1.4054169
Published Online: June 7, 2022
View Article titled, Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant
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Topics: Design, Nondestructive evaluation, Nuclear power stations, Safety
Journal Articles

Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things

M. Zorkany, Hassan F. Morsi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031901.
Paper No: NERS-20-1010
https://doi.org/10.1115/1.4048113
Published Online: May 27, 2022
View Article titled, Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things
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Topics: Heat, Radioactive substances, Safety, Security, Transportation systems, Internet of things, Embedded systems, Sensors, Vehicles, Radiation (Physics)
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
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
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

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Article titled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years

Matjaž Žvar, Tomaž Žagar
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.
Paper No: NERS-21-1022
https://doi.org/10.1115/1.4052013
Published Online: March 16, 2022
View Article titled, Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years
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Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels