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Journal Articles

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

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: April 22, 2024
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
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Topics: Boiling water reactors, Hydrogen, Oxidation, Simulation, Uncertainty analysis, Zirconium, Accidents, Sensitivity analysis, Temperature, Uncertainty
Journal Articles

Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

Daniel T. Wojtaszek, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031302.
Paper No: NERS-23-1090
https://doi.org/10.1115/1.4064581
Published Online: April 17, 2024
View Article titled, Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
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Topics: Fuels, Hydrogen, Temperature, Very high temperature reactors, Uranium, Manufacturing
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

Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 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: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics
Journal Articles

Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility

Bhuvaneshwar Gera, Pavan K. Sharma, Aditya Karanam, Shubham Mishra, I. Thangamani, Nandan Saha, Anu Dutta, Priyanshu Goyal, Vishnu Verma, Jayanta Chattopadhyay
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021701.
Paper No: NERS-22-1118
https://doi.org/10.1115/1.4063239
Published Online: October 20, 2023
View Article titled, Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility
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Topics: Containment, Errors, Helium, Hydrogen
Journal Articles

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

Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

Hydrogen Loading System for Thin Films for Betavoltaics

Darrell Cheu, Thomas Adams, Shripad Revankar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041109.
Paper No: NERS-22-1172
https://doi.org/10.1115/1.4056974
Published Online: March 13, 2023
View Article titled, Hydrogen Loading System for Thin Films for Betavoltaics
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Topics: Hydrogen, Palladium, Temperature, Leakage, Pressure drop, Thin films
Journal Articles

Water Hammers Exploded the Nuclear Power Plants at Fukushima Daiichi

Robert A. Leishear
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Expert View
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014702.
Paper No: NERS-21-1058
https://doi.org/10.1115/1.4054004
Published Online: June 10, 2022
View Article titled, Water Hammers Exploded the Nuclear Power Plants at Fukushima Daiichi
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Topics: Explosions, Hydrogen, Water
Journal Articles

Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics

Ahsan Khan, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012001.
Paper No: NERS-21-1153
https://doi.org/10.1115/1.4054117
Published Online: June 7, 2022
View Article titled, Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics
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Topics: Computational fluid dynamics, Hydrogen, Temperature, Plates (structures)
Journal Articles

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

Alain Flores y Flores, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201.
Paper No: NERS-20-1034
https://doi.org/10.1115/1.4048006
Published Online: May 27, 2022
View Article titled, Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
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Topics: Explosions, Hydrogen, Aerosols, Thermal hydraulics, Pressure, Flames, Test facilities
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
Publisher: ASME
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

Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction

K. Khumsa-Ang, S. Rousseau, O. Shiman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031102.
Paper No: NERS-21-1065
https://doi.org/10.1115/1.4052520
Published Online: March 15, 2022
View Article titled, Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction
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Topics: Alloys, Coatings, Corrosion, Hydrogen, Water, Weight (Mass), Zirconium, Absorption, Coating processes, Zirconium alloys
Journal Articles

Guest Editorial by Gilles Rodriguez

Gilles Rodriguez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303.
Paper No: NERS-21-1137
https://doi.org/10.1115/1.4052719
Published Online: December 14, 2021
View Article titled, Guest Editorial by Gilles Rodriguez
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Topics: Carbon, Collaboration, Economics , Energy consumption, Heat, Hydrogen, Industrial capacity, Innovation, Manufacturing systems, Molten salt reactors
Journal Articles

Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

S. T. Langille, C. E. Coleman, G. A. McRae
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031801.
Paper No: NERS-20-1069
https://doi.org/10.1115/1.4048313
Published Online: April 1, 2021
View Article titled, Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?
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Topics: Hydrogen, Pressure, Yttrium, Zirconium, Stainless steel, Fittings
Journal Articles

The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3

Pavel Kůs, Martin Kronďák, Martin Skala, Alena Kobzová, Petr Brabec, Patricie Halodová, Janka Mihóková, Štefan Tkáč, Anna Černá
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021804.
Paper No: NERS-20-1149
https://doi.org/10.1115/1.4049281
Published Online: January 28, 2021
View Article titled, The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3
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Topics: Circuits, Nuclear power stations, Hydrogen, Magnetite, Water, Microscopy
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
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021604.
Paper No: NERS-20-1110
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

A Study on Sodium–Concrete Reaction in Presence of Internal Heating

Munemichi Kawaguchi, Shinya Miyahara, Masayoshi Uno
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021106.
Paper No: NERS-19-1119
https://doi.org/10.1115/1.4045898
Published Online: February 3, 2020
View Article titled, A Study on Sodium–Concrete Reaction in Presence of Internal Heating
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Topics: Concretes, Sodium, Temperature, Aerosols, Heating, Ablation (Vaporization technology), Hydrogen
Journal Articles

The Autoignition of Nuclear Reactor Power Plant Explosions

Robert A. Leishear
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technology Review
ASME J of Nuclear Rad Sci. January 2020, 6(1): 014001.
Paper No: NERS-18-1021
https://doi.org/10.1115/1.4044807
Published Online: November 29, 2019
View Article titled, The Autoignition of Nuclear Reactor Power Plant Explosions
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Topics: Explosions, Hydrogen
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
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.
Paper No: NERS-18-1017
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

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Martín Lemes, Alicia Denis, Alejandro Soba
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020903.
Paper No: NERS-18-1078
https://doi.org/10.1115/1.4042705
Published Online: March 15, 2019
View Article titled, Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
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Topics: Accidents, Cladding systems (Building), Coolants, Fuel rods, Fuels, High temperature, Hydrogen, Simulation, Temperature, Water
Journal Articles

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Felix Boldt
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.
Paper No: NERS-18-1065
https://doi.org/10.1115/1.4042118
Published Online: March 15, 2019
View Article titled, Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
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Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation