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Journal Articles

Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced With Cellulose Nanofibrils and Graphene Oxide

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Nur Atiqah Syahirah Shari, Mohammad Khairul Azhar Abdul Razab, An'amt Mohamed Noor, Mohd Zahri Abdul Aziz, Nor Hakimin Abdullah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031004.
Paper No: NERS-24-1102
https://doi.org/10.1115/1.4068121
Published Online: April 10, 2025
View Articletitled, Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced With Cellulose Nanofibrils and Graphene Oxide
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Topics: Bricks, Cellulose, Composite materials, Graphene, X-ray diffraction, Testing, Bagasse, Machinery, Mechanical properties
Journal Articles

Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code

Open Access
E. B. Mweze, J. L. Muswema, G. B. Ekoko, D. G. Kom'bele
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031501.
Paper No: NERS-24-1090
https://doi.org/10.1115/1.4067996
Published Online: March 18, 2025
View Articletitled, Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code
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Topics: Neutrons, Nuclear reactors, Rods, Safety, Transients (Dynamics), Model validation, Errors, Neutron flux, Probability, Testing
Journal Articles

Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions

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German Cota-Sanchez, Lin Xiao, Stephane Rousseau
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031107.
Paper No: NERS-22-1007
https://doi.org/10.1115/1.4054637
Published Online: May 25, 2022
View Articletitled, Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions
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Topics: Corrosion, Welding, Phase diagrams, Water, Welded joints, Testing
Journal Articles

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

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A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
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 Articletitled, 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

A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

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Venkata Rajesh Saranam, Peter Carter, Kyle A. Rozman, Ömer N. Doğan, Brian K. Paul
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021302.
Paper No: NERS-20-1185
https://doi.org/10.1115/1.4050421
Published Online: October 19, 2021
View Articletitled, A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications
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Topics: Bonding, Creep, Design, Diffusion bonding (Metals), Fatigue, Heat exchangers, Rupture, Temperature, Stress, Pressure
Journal Articles

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Free
Fidelma G. Di Lemma, Colby B. Jensen, Joshua J. Kane, Wei-Ying Chen, Xiang Liu, Luca Capriotti, Cynthia A. Adkins, Boopathy Kombaiah, Alexander J. Winston, Lingfeng He, Daniel Wachs
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041602.
Paper No: NERS-20-1097
https://doi.org/10.1115/1.4049721
Published Online: April 22, 2021
View Articletitled, Metallic Fast Reactor Separate Effect Studies for Fuel Safety
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Topics: Bubbles, Fuels, Instrumentation, Irradiation (Radiation exposure), Nuclear fission, Safety, Transients (Dynamics), Sodium fast reactors, Testing, Fast neutron reactors
Journal Articles

Testing and Validation of Nuclear Fuel Composition Using SIMS Method

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Ivan Elantyev, Michal Kostal, Evzen Losa, Kristina Sihelska, Klara Rezankova, Jan Lorincik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022002.
Paper No: NERS-20-1155
https://doi.org/10.1115/1.4049097
Published Online: January 28, 2021
View Articletitled, Testing and Validation of Nuclear Fuel Composition Using SIMS Method
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Topics: Particulate matter, Secondary ion mass spectrometry, Uranium, Fuels, Nuclear fuels, Testing
Journal Articles

Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods

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J. Veselá, P. Mareš, P. Zahrádka, J. Patera
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024504.
Paper No: NERS-20-1101
https://doi.org/10.1115/1.4048479
Published Online: November 16, 2020
View Articletitled, Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods
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Topics: Blades, Fracture (Materials), Steam turbines, Surface cracks, Testing, Ultrasonic testing, Corrosion, Turbine blades, Magnetic particles, Eddies (Fluid dynamics)
Journal Articles

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

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Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.
Paper No: NERS-20-1093
https://doi.org/10.1115/1.4048239
Published Online: November 16, 2020
View Articletitled, On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application
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Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams
Journal Articles

Manipulation System for Measuring Heat Flux in Radioactive Melt

Available to Purchase
Michal Knedlík, David Rot, Jan Hrbek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021801.
Paper No: NERS-20-1140
https://doi.org/10.1115/1.4048632
Published Online: October 30, 2020
View Articletitled, Manipulation System for Measuring Heat Flux in Radioactive Melt
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Topics: Control algorithms, Electromagnetic induction, Heat flux, Manipulators, Melting, Safety, Temperature, Testing, User interfaces, Computer software
Journal Articles

Testing Oxygen Nuclear Data Libraries in Research Center Rez

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Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Luiz Leal
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021501.
Paper No: NERS-20-1017
https://doi.org/10.1115/1.4048763
Published Online: October 30, 2020
View Articletitled, Testing Oxygen Nuclear Data Libraries in Research Center Rez
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Topics: Neutrons, Oxygen, Spectra (Spectroscopy), Water, Testing, Fuels, Neutron sources, Leakage
Journal Articles

Ni + and He + Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy

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Maisaa N. Tawfeeq, Robert J. Klassen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011602.
Paper No: NERS-19-1135
https://doi.org/10.1115/1.4046716
Published Online: October 1, 2020
View Articletitled, Ni + and He + Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy
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Topics: Alloys, Damage, Electron microscopy, Hardening, Heat, Helium, Ion implantation, Irradiation (Radiation exposure), Superalloys, Testing
Journal Articles

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

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Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.
Paper No: NERS-19-1161
https://doi.org/10.1115/1.4047113
Published Online: September 4, 2020
View Articletitled, 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

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

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T. Beuthe, A. Vasić, H. Zahlan, A. Nava Domínguez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115.
Paper No: NERS-20-1002
https://doi.org/10.1115/1.4047288
Published Online: June 5, 2020
View Articletitled, Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors
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Topics: Heat transfer, Modeling, Pressure, Supercritical water reactors, Temperature, Simulation, Accidents, Testing, Water, Transients (Dynamics)
Journal Articles

Tensioned Metastable Fluid Detectors for Spectrometric Radon–Progeny Detection and AARST-NRPP Standard Qualification

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Mitch P. Hemesath, Brian C. Archambault, Nathan M. Boyle, Rusi P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 042001.
Paper No: NERS-19-1106
https://doi.org/10.1115/1.4045691
Published Online: June 3, 2020
View Articletitled, Tensioned Metastable Fluid Detectors for Spectrometric Radon–Progeny Detection and AARST-NRPP Standard Qualification
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Topics: Errors, Fluids, Pressure, Sensors, Temperature, Air flow, Algorithms, Testing, Radiation (Physics)
Journal Articles

A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector

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William Kyffin, David Gandy, Barry Burdett
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021116.
Paper No: NERS-18-1112
https://doi.org/10.1115/1.4044752
Published Online: January 29, 2020
View Articletitled, A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector
Open the PDF for A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector in another window
Topics: ASTM International, Fracture toughness, Hot pressing, Manufacturing, Materials properties, Oxygen, Stainless steel, Supply chains, Temperature, Tensile strength
Journal Articles

Radiographic Nondestructive Testing Simulations Using gate Software Toolkit

Available to Purchase
Eslam Taha, M. S. Mohammed, Essam Banoqitah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011901.
Paper No: NERS-18-1127
https://doi.org/10.1115/1.4044909
Published Online: November 29, 2019
View Articletitled, Radiographic Nondestructive Testing Simulations Using gate Software Toolkit
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Topics: Computer software, Gates (Closures), Nondestructive evaluation, Radiation (Physics), Simulation, Testing, Wedges, X-rays, Gamma rays, Emissions
Journal Articles

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

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I. K. Baidoo, J. Zou, B. Li, J. Song, B. Wu, Q. Yang, Z. Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041402.
Paper No: NERS-18-1123
https://doi.org/10.1115/1.4043100
Published Online: July 19, 2019
View Articletitled, Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments
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Topics: Atoms, Displacement, Dosimetry, Fluence (Radiation measurement), Fuels, Geometry, Iron, Manufacturing, Modeling, Neutron flux
Journal Articles

Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor

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Michal Košťál, Zdeněk Matěj, Filip Mravec, František Cvachovec, Martin Schulc, Vlastimil Juříček, Vojtěch Rypar, Jaroslav Šoltés, Evžen Losa, Ladislav Viererbl
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030915.
Paper No: NERS-18-1054
https://doi.org/10.1115/1.4043197
Published Online: May 29, 2019
View Articletitled, Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor
Open the PDF for Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor in another window
Topics: Neutrons, Scintillation counters, Silicon, Spectra (Spectroscopy), Testing, Neutron beams, Resolution (Optics)
Journal Articles

Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

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Anna Hojna, Mariia Zimina, Lucia Rozumova
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030909.
Paper No: NERS-19-1017
https://doi.org/10.1115/1.4043099
Published Online: May 10, 2019
View Articletitled, Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water
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Topics: Fracture (Materials), Polishing, Pressurized water reactors, Steel, Stress, Water, Fracture (Process), Testing, Grinding