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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
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Topics: Coatings, Flow (Dynamics), High temperature, Liquid metals, Manufacturing, Performance characterization, Insulation, Coolants, Corrosion, Fusion reactors
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
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Topics: Design, High temperature, Thermal hydraulics, Fuels, Coolants, Temperature, Cycles, Engineering simulation, Flow (Dynamics), Simulation
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
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Topics: Eddies (Fluid dynamics), Eddy currents (Electricity), Flowmeters, High temperature, Sodium, Sensors, Flow (Dynamics), Liquid metals, Coolants, Engineering prototypes
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
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Topics: Gaskets, Graphite, Leakage, Temperature, Relaxation (Physics), High temperature, Weight (Mass), Stress
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
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Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling
Journal Articles

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.
Paper No: NERS-21-1118
DOI: https://doi.org/10.1115/1.4054079
Published Online: May 26, 2022
View Article titled, Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels
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Topics: Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature
Journal Articles

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Wolfgang Hering, Joachim Fuchs, Alexandru Onea, Sara Perez-Martin, Thomas Schaub
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.
Paper No: NERS-21-1031
DOI: https://doi.org/10.1115/1.4052642
Published Online: December 7, 2021
View Article titled, Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
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Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation
Journal Articles

Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher

Alexandre Lecoanet, Michel Gradeck, Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer, Frédéric Payot, Christophe Journeau, Nicolas Rimbert
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011308.
Paper No: NERS-21-1042
DOI: https://doi.org/10.1115/1.4051448
Published Online: August 3, 2021
View Article titled, Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher
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Topics: Ablation (Vaporization technology), Heat transfer, Melting, Sodium fast reactors, Cavities, High temperature, Ice, Design, Temperature, Water
Journal Articles

Small Modular Reactors: Learning From the Past

Esam M. A. Hussein
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034508.
Paper No: NERS-20-1152
DOI: https://doi.org/10.1115/1.4050478
Published Online: May 26, 2021
View Article titled, Small Modular Reactors: Learning From the Past
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Topics: Coolants, Fast neutron reactors, Fuels, Gas cooled reactors, High temperature, Liquid metals, Molten salt reactors, Pressurized water reactors, Small modular reactors, Licensing
Journal Articles

Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

Petra Gávelová, Patricie Halodová, Daniela Marušáková, Ondřej Libera, Jakub Krejčí, Věra Vrtílková
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021604.
Paper No: NERS-20-1110
DOI: https://doi.org/10.1115/1.4049053
Published Online: December 14, 2020
View Article titled, Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation
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Topics: Cladding systems (Building), High temperature, Hydrogen, Nanoindentation, Oxidation, Oxygen, Temperature, Zirconium, Accidents
Journal Articles

Methodology for Measurement of Density of Liquid Oxides

Jan Hrbek, Bence Mészáros, Mykhaylo Paukov, Martin Kudláč
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021601.
Paper No: NERS-20-1074
DOI: https://doi.org/10.1115/1.4048478
Published Online: November 16, 2020
View Article titled, Methodology for Measurement of Density of Liquid Oxides
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Topics: Density, Temperature, Electromagnetic induction, High temperature
Journal Articles

Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

S. Majumdar, J. Kishor, A. N. Behera, B. Vishwanadh, A. Borgohain, R. Kapoor, R. Tewari, V. Kain, Madangopal Krishnan, G. K. Dey, S. Banerjee
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603.
Paper No: NERS-19-1177
DOI: https://doi.org/10.1115/1.4047919
Published Online: October 2, 2020
View Article titled, Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
Open the PDF for Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors in another window
Topics: Alloys, Creep, Errors, Cathode ray oscilloscopes, Electron beams, High temperature, Corrosion, Melting
Journal Articles

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.
Paper No: NERS-19-1161
DOI: https://doi.org/10.1115/1.4047113
Published Online: September 4, 2020
View Article titled, ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors
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Topics: Design, Diffusion (Physics), Heat exchangers, High temperature, Reliability, Testing, Construction, ASME Standards, ASME Boiler and Pressure Vessel Code, Stress
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
DOI: 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

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.
Paper No: NERS-19-1059
DOI: https://doi.org/10.1115/1.4044910
Published Online: February 5, 2020
View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
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Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)
Journal Articles

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401.
Paper No: NERS-17-1237
DOI: https://doi.org/10.1115/1.4045125
Published Online: November 29, 2019
View Article titled, Experimental Investigation on Flash Evaporation Related to Pipe Leakage
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Topics: Evaporation, Flow (Dynamics), High temperature, Leakage, Pipes, Pressure, Sensors, Sprays, Temperature, Temperature distribution
Journal Articles

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Bingjie Xiao, Xiao Huang, Qi Yang, Prakash Patnaik
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041204.
Paper No: NERS-18-1081
DOI: https://doi.org/10.1115/1.4042500
Published Online: July 19, 2019
View Article titled, Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application
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Topics: Alloys, Coatings, Oxidation, Pressure, Steam, Superheating, Temperature, Water, Weight (Mass), High temperature
Journal Articles

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Petra Gávelová, Patricie Halodová, Hygreeva Kiran Namburi, Iveta Adéla Prokůpková, Marek Mikloš, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.
Paper No: NERS-18-1017
DOI: https://doi.org/10.1115/1.4043462
Published Online: May 3, 2019
View Article titled, From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
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Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)
Journal Articles

Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030301.
Paper No: NERS-19-1035
DOI: https://doi.org/10.1115/1.4043382
Published Online: April 19, 2019
View Article titled, Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018
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Topics: Accidents, Circuits, Coolants, Corrosion, Generation IV reactors, Materials research, Modeling, Nuclear engineering, Nuclear fuel cycle, Nuclear reactors
Journal Articles

Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR

Tetsuaki Takeda
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021003.
Paper No: NERS-17-1288
DOI: https://doi.org/10.1115/1.4041690
Published Online: March 15, 2019
View Article titled, Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR
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Topics: Gases, High temperature, Natural convection, Numerical analysis, Temperature, Diffusion (Physics), Flow (Dynamics), Very high temperature reactors, Low temperature, Fluids