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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
DOI: 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
Click here to open pdf in another window 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
Topics: Coatings, Flow (Dynamics), High temperature, Liquid metals, Manufacturing, Performance characterization, Insulation, Coolants, Corrosion, Fusion reactors
Journal Articles

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

Accepted Manuscript
Lekhnath Ghimire, Edward Waller
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1006
DOI: https://doi.org/10.1115/1.4062644
Published Online: May 27, 2023
View Article titled, Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production
Click here to open pdf in another window PDF for Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production
Topics: Energy generation, Small modular reactors, Safety, Arctic region, Design, Accidents, Climate, Construction, Electric power generation, Fuels
Journal Articles

Main Parameters Influencing The Level Of Labile Contamination And The Removal Factor

Accepted Manuscript
Pierrick Agullo, Alban Gossard, Gilles Ranchoux, Emmanuel Porcheron, Fabrice Petitot
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1160
DOI: https://doi.org/10.1115/1.4062550
Published Online: May 18, 2023
View Article titled, Main Parameters Influencing The Level Of Labile Contamination And The Removal Factor
Click here to open pdf in another window PDF for Main Parameters Influencing The Level Of Labile Contamination And The Removal Factor
Topics: Contamination, Surface roughness, Cutting, Drying, Feedback, Nuclear decommissioning, Nuclear environmental management, Nuclear power stations, Particulate matter, Pressure
Journal Articles

System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept

Accepted Manuscript
Shu Jun Wang, Xianmin Huang, Blair Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1011
DOI: https://doi.org/10.1115/1.4062500
Published Online: May 5, 2023
View Article titled, System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept
Click here to open pdf in another window PDF for System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept
Topics: Design, High temperature, Thermal hydraulics, Fuels, Coolants, Temperature, Cycles, Engineering simulation, Flow (Dynamics), Simulation
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
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041501.
Paper No: NERS-22-1145
DOI: 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
Click here to open pdf in another window PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Journal Articles

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Accepted Manuscript
Nico Krauter, Alexandru Onea, Gunter Gerbeth, Sven Eckert
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1185
DOI: https://doi.org/10.1115/1.4062239
Published Online: March 31, 2023
View Article titled, Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
Click here to open pdf in another window PDF for Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Flowmeters, High temperature, Sodium, Sensors, Flow (Dynamics), Liquid metals, Coolants, Engineering prototypes
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-22-1136
DOI: https://doi.org/10.1115/1.4056854
Published Online: March 14, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
Click here to open pdf in another window PDF for Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)
Journal Articles

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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
Paper No: NERS-22-1119
DOI: https://doi.org/10.1115/1.4056930
Published Online: March 13, 2023
View Article titled, Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
Click here to open pdf in another window PDF for Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
Journal Articles

Hydrogen Loading System for Thin Films for Betavoltaics

Darrell Cheu, Thomas Adams, Shripad Revankar
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501.
Paper No: NERS-22-1172
DOI: https://doi.org/10.1115/1.4056974
Published Online: March 13, 2023
View Article titled, Hydrogen Loading System for Thin Films for Betavoltaics
Click here to open pdf in another window PDF for Hydrogen Loading System for Thin Films for Betavoltaics
Topics: Hydrogen, Palladium, Temperature, Leakage, Pressure drop, Thin films
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041301.
Paper No: NERS-22-1165
DOI: https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Article titled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
Click here to open pdf in another window PDF for ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.
Paper No: NERS-21-1161
DOI: https://doi.org/10.1115/1.4056834
Published Online: March 2, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
Click here to open pdf in another window PDF for Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
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
DOI: 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
Click here to open pdf in another window PDF for 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
Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection
Journal Articles

Long-Term Performance of Semimetallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.
Paper No: NERS-22-1036
DOI: https://doi.org/10.1115/1.4056260
Published Online: February 8, 2023
View Article titled, Long-Term Performance of Semimetallic Gaskets
Click here to open pdf in another window PDF for Long-Term Performance of Semimetallic Gaskets
Topics: Gaskets, Graphite, Leakage, Temperature, Relaxation (Physics), High temperature, Weight (Mass), Stress
Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
DOI: https://doi.org/10.1115/1.4056463
Published Online: February 8, 2023
View Article titled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
Click here to open pdf in another window PDF for Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods
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

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

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

Markus Petroff, Rudi Kulenovic, Jörg Starflinger
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041702.
Paper No: NERS-21-1028
DOI: https://doi.org/10.1115/1.4051876
Published Online: September 3, 2022
View Article titled, Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection
Click here to open pdf in another window PDF for Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection
Topics: Floods, Particulate matter, Quenching (Metalworking), Temperature, Test facilities, Water, Flow (Dynamics), Concretes
Journal Articles

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003.
Paper No: NERS-22-1044
DOI: https://doi.org/10.1115/1.4055012
Published Online: September 1, 2022
View Article titled, Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating
Click here to open pdf in another window PDF for Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating
Topics: Boron, Coatings, Fuels, Temperature, Cladding systems (Building), Neutrons, Accidents
Journal Articles

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Rolando Calabrese
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041603.
Paper No: NERS-21-1027
DOI: https://doi.org/10.1115/1.4054941
Published Online: September 1, 2022
View Article titled, The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations
Click here to open pdf in another window PDF for The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations
Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling
Journal Articles

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401.
Paper No: NERS-22-1006
DOI: https://doi.org/10.1115/1.4054842
Published Online: July 19, 2022
View Article titled, Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate
Click here to open pdf in another window PDF for Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate
Topics: Flow (Dynamics), Steam, Temperature, Turbulence, Condensation, Flat plates, Boundary layer turbulence, Computational fluid dynamics, Computation
Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.
Paper No: NERS-21-1018
DOI: https://doi.org/10.1115/1.4054514
Published Online: June 24, 2022
View Article titled, Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
Click here to open pdf in another window PDF for Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity