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Journal Articles

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Accepted Manuscript
Armando Nava Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: September 13, 2024
View Article titled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Computers, Fuels, Manufacturing, Nuclear fuels, Nuclear industry, Supercritical fluids, Water
Journal Articles

Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach

Dipanjan Ray, Satya Prakash Saraswat, Vikesh Singh Bhadouria
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041501.
Paper No: NERS-23-1097
https://doi.org/10.1115/1.4065893
Published Online: July 16, 2024
View Article titled, Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
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Topics: Diffusion (Physics), Fuels, Geometry, Neutron flux, Neutrons, Scalars, Waves, Nuclear fuels, Design, 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
Publisher: ASME
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

Testing and Validation of Nuclear Fuel Composition Using SIMS Method

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 Article titled, 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

The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

Lian-Cheng Wang, Matthew H. Kaye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011601.
Paper No: NERS-19-1094
https://doi.org/10.1115/1.4046784
Published Online: October 1, 2020
View Article titled, The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System
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Topics: Nuclear fuels, Phase diagrams, Temperature, Uranium, Modeling, Military systems, Nuclear fission, Spent nuclear fuels
Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.
Paper No: NERS-19-1046
https://doi.org/10.1115/1.4044751
Published Online: November 8, 2019
View Article titled, Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
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Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient
Journal Articles

Rod Bow Ultrasonic Measurements Possibilities

Marcin Kopeć, Martina Malá
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030901.
Paper No: NERS-18-1044
https://doi.org/10.1115/1.4041277
Published Online: April 16, 2019
View Article titled, Rod Bow Ultrasonic Measurements Possibilities
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Topics: Fuel rods, Probes, Inspection, Ultrasonic measurement, Fuels, Radiation (Physics), Nuclear fuels
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

Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U 3 O 8 -Al, U 3 Si 2 -Al, and UN-Al

Jayangani I. Ranasinghe, Ericmoore Jossou, Linu Malakkal, Barbara Szpunar, Jerzy A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031020.
Paper No: NERS-17-1304
https://doi.org/10.1115/1.4039886
Published Online: May 16, 2018
View Article titled, Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U 3 O 8 -Al, U 3 Si 2 -Al, and UN-Al
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Topics: Fuels, Nuclear fuels, Thermal conductivity, Temperature, Temperature gradient, Temperature profiles
Journal Articles

COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Vefa N. Kucukboyaci, Liping Cao, Yixing Sung
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031002.
Paper No: NERS-15-1018
https://doi.org/10.1115/1.4032594
Published Online: June 17, 2016
View Article titled, COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
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Topics: Accidents, Coolants, Critical heat flux, Fuel rods, Fuels, Heat transfer, Irradiation (Radiation exposure), Pressurized water reactors, Simulation, Transients (Dynamics)
Journal Articles

European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests

Radek Novotný, Přemysl Janík, Aki Toivonen, Anna Ruiz, Zoltan Szaraz, Lefu Zhang, Jan Siegl, Petr Haušild, Sami Penttilä, Jan Macák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031007.
Paper No: NERS-15-1097
https://doi.org/10.1115/1.4032871
Published Online: June 17, 2016
View Article titled, European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests
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Topics: Corrosion, Corrosion resistance, Finishes, Flow (Dynamics), Fuels, Oxygen, Stainless steel, Supercritical water reactors, Temperature, Water
Journal Articles

Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

Csaba Maráczy, György Hegyi, István Trosztel, Emese Temesvári
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011004.
Paper No: NERS-15-1041
https://doi.org/10.1115/1.4030933
Published Online: December 9, 2015
View Article titled, Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor
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Topics: Fuels, Nuclear fuels, Safety, Scram, Temperature, Water, Pressure, Steady state, Test facilities, Fuel rods
Journal Articles

Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading

Noah A. Weichselbaum, Morteza Rahimi Abkenar, Marcos Vanella, Majid T. Manzari, Elias Balaras, Philippe M. Bardet
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041005.
Paper No: NERS-15-1013
https://doi.org/10.1115/1.4031031
Published Online: September 16, 2015
View Article titled, Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading
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Topics: Computation, Engineering prototypes, Engineering simulation, Flow (Dynamics), Fluids, Fuel rods, Fuels, Geometry, Manufacturing, Nuclear fuels
Journal Articles

Investigation of Natural Convection Heat-Transfer Phenomena in Packed Beds: Lead-Way Toward New Nuclear Fuel Design

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041014.
Paper No: NERS-15-1007
https://doi.org/10.1115/1.4030983
Published Online: September 3, 2015
View Article titled, Investigation of Natural Convection Heat-Transfer Phenomena in Packed Beds: Lead-Way Toward New Nuclear Fuel Design
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Topics: Design, Heat transfer, Particulate matter, Heat, Fuels, Nuclear fuels, Temperature, Cladding systems (Building)