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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
Article Type: Research-Article
Publisher: ASME
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

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
Open the PDF for Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts with a Hydrogen-based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor in another window
Topics: Fuels, Hydrogen, Physics, Small modular reactors, Rods, Temperature, Coolants, Design, High temperature, Molten salt reactors
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

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

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
Publisher: ASME
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103.
Paper No: NERS-22-1137
https://doi.org/10.1115/1.4056772
Published Online: May 31, 2023
View Article titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
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Topics: Coolants, Design, Diluents, Fuels, Leakage, Neutrons, Supercritical carbon dioxide, Nuclear fission, Nuclides, Feedback
Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
Publisher: ASME
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Article titled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
Open the PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel in another window
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
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

Novel Eddy Current Array Sensor Delivery Tool for Automated Nondestructive Examination of Spent Fuel Pool Liner

Michael Smith, Emily Abbate, Joey Phillips, Byungsik Yoon
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021701.
Paper No: NERS-21-1165
https://doi.org/10.1115/1.4055065
Published Online: September 2, 2022
View Article titled, Novel Eddy Current Array Sensor Delivery Tool for Automated Nondestructive Examination of Spent Fuel Pool Liner
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Topics: Design, Eddies (Fluid dynamics), Eddy currents (Electricity), Inspection, Motors, Nondestructive evaluation, Sensors, Spent nuclear fuels, Rails, Railroad passenger cars
Journal Articles

Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

Jindong Zhang, Chongzhi Wu
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011801.
Paper No: NERS-22-1014
https://doi.org/10.1115/1.4054878
Published Online: July 19, 2022
View Article titled, Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant
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Topics: Construction, Design, Evaluation methods, Nuclear power stations, Failure mechanisms, Nuclear power
Journal Articles

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
https://doi.org/10.1115/1.4053827
Published Online: June 15, 2022
View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors
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

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

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Emmanuel K. Boafo, Emmanuel Numapau Gyamfi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.
Paper No: NERS-21-1094
https://doi.org/10.1115/1.4053050
Published Online: May 26, 2022
View Article titled, Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA
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Topics: Accidents, Hydrogen, Sensitivity analysis, Uncertainty, Uncertainty quantification, Uncertainty analysis, Design, Optimization
Journal Articles

Suggestion on Improving Small Branch BOSS Joints Welding Quality

Chongzhi Wu, Ruifeng Zhu, Pengteng Yu, Haoming Sun, Qingli Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Discussions
ASME J of Nuclear Rad Sci. July 2022, 8(3): 035501.
Paper No: NERS-21-1095
https://doi.org/10.1115/1.4053690
Published Online: May 26, 2022
View Article titled, Suggestion on Improving Small Branch BOSS Joints Welding Quality
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Topics: Design, Nondestructive evaluation, Welding