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Journal Articles

Operation Optimization Framework for Advanced Reactors Using a Data Driven Digital Twin

Accepted Manuscript
Andy Rivas, Gregory Delipei, Jason Hou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1017
https://doi.org/10.1115/1.4066777
Published Online: October 4, 2024
View Article titled, Operation Optimization Framework for Advanced Reactors Using a Data Driven Digital Twin
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Topics: Digital twin, Optimization, Maintenance, Nuclear reactors, Actuators, Artificial intelligence, Bayesian network, Carbon, Feedforward neural networks, Genetic algorithms
Journal Articles

Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

Jason L. Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William A. Hanson, Nicholas Ullum, Jeffrey Giglio, James I. Cole
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031601.
Paper No: NERS-23-1114
https://doi.org/10.1115/1.4064779
Published Online: April 17, 2024
View Article titled, Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
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Topics: Bending strength, Density, Fuels, Mechanical properties, Nuclear fission, Porosity, Stress, Young's modulus, Zirconium, Alloys
Journal Articles

Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding

Hakan Ozaltun, James I. Cole, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021601.
Paper No: NERS-23-1048
https://doi.org/10.1115/1.4063163
Published Online: November 1, 2023
View Article titled, Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Irradiation (Radiation exposure), Plates (structures), Deformation
Journal Articles

Long-Term Performance of Semimetallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.
Paper No: NERS-22-1036
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 Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-Pueng, Yanin Sukjai
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.
Paper No: NERS-21-1156
https://doi.org/10.1115/1.4054546
Published Online: June 15, 2022
View Article titled, The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)
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Topics: Airfoils, Flow (Dynamics), Geometry, Stress, Heat exchangers, Heat transfer, Temperature, Fluids, Structural analysis
Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.
Paper No: NERS-20-1206
https://doi.org/10.1115/1.4053689
Published Online: May 26, 2022
View Article titled, Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations
Journal Articles

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.
Paper No: NERS-21-1100
https://doi.org/10.1115/1.4052808
Published Online: May 26, 2022
View Article titled, Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste
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Topics: Fuels, Heat, Nuclear power stations, Plastics, Pyrolysis, Small modular reactors, Heating, Syngas, Temperature, Biochar
Journal Articles

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Yue Zou, Brian Derreberry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.
Paper No: NERS-21-1040
https://doi.org/10.1115/1.4053013
Published Online: May 26, 2022
View Article titled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities
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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification
Journal Articles

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.
Paper No: NERS-21-1087
https://doi.org/10.1115/1.4054557
Published Online: May 17, 2022
View Article titled, Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
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Topics: Alloys, Extruding, Friction welding, Zirconium alloys, Stainless steel, Bearings, Zirconium, Friction, Nickel, Supercritical water reactors
Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.
Paper No: NERS-21-1030
https://doi.org/10.1115/1.4052519
Published Online: March 22, 2022
View Article titled, Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code
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Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress
Journal Articles

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.
Paper No: NERS-21-1082
https://doi.org/10.1115/1.4052590
Published Online: March 15, 2022
View Article titled, Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
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Topics: Computational fluid dynamics, Heat transfer, Stress, Supercritical water reactors, Temperature, Fuels, Small modular reactors
Journal Articles

A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

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 Article titled, 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

Backfill of Radioactive Waste Disposal: Feasibility Study of Argillite/Bentonite (COx/MX80) Pellets

Danai Tyri, Bui Quoc Huy Ly, François Nader, Irini Djeran-Maigre, Jean-Claude Robinet, Jad Zghondi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041901.
Paper No: NERS-20-1091
https://doi.org/10.1115/1.4050296
Published Online: April 22, 2021
View Article titled, Backfill of Radioactive Waste Disposal: Feasibility Study of Argillite/Bentonite (COx/MX80) Pellets
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Topics: Density, Pelletizing, Water, Machinery, Manufacturing, Stress, Optimization
Journal Articles

Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities

Kalpesh Joshi, Bikash Poudel, Ramakrishna (Rama) Gokaraju
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031303.
Paper No: NERS-20-1051
https://doi.org/10.1115/1.4048896
Published Online: March 16, 2021
View Article titled, Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities
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Topics: Design, Nuclear power stations, Simulation, Small modular reactors, Stress, Turbines, Power systems (Machinery), Governors, Steady state, Flow (Dynamics)
Journal Articles

Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

Emmanuel O. Osigwe, Arnold Gad-Briggs, Mafel Obhuo, Pericles Pilidis
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031301.
Paper No: NERS-19-1139
https://doi.org/10.1115/1.4048903
Published Online: February 19, 2021
View Article titled, Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant
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Topics: Closed-cycle gas turbines, Compressors, Control systems, Cycles, Fluids, Pressure, Storage tanks, Stress, Temperature, Valves
Journal Articles

Basic Microstructural Characterization of Second Phases in Homogeneous Weld Joint Made of X6CrNiNbN25-20 Steel After Long-Term Exposure Time at 973 K

Jakub Řehořek, Hygreeva Kiran Namburi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024505.
Paper No: NERS-20-1113
https://doi.org/10.1115/1.4048900
Published Online: November 16, 2020
View Article titled, Basic Microstructural Characterization of Second Phases in Homogeneous Weld Joint Made of X6CrNiNbN25-20 Steel After Long-Term Exposure Time at 973 K
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Topics: Creep, Rupture, Steel, Particulate matter, Stress, Grain size, Heat treating (Metalworking), Grain boundaries, Etching, Heat
Journal Articles

Mechanical Tests Results of Laser Shock Peening-Treated Austenitic Steel

Zbyněk Špirit, Jan Kaufman, Michal Chocholoušek, Josef Strejcius
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024506.
Paper No: NERS-20-1135
https://doi.org/10.1115/1.4048766
Published Online: November 16, 2020
View Article titled, Mechanical Tests Results of Laser Shock Peening-Treated Austenitic Steel
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Topics: Fatigue life, Laser hardening, Lasers, Shock (Mechanics), Shot peening, Stainless steel, Steel, Mechanical testing, Stress, Pressure
Journal Articles

Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR

Ashok Kumar, Anindya Chatterjee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011801.
Paper No: NERS-20-1001
https://doi.org/10.1115/1.4047494
Published Online: October 5, 2020
View Article titled, Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR
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Topics: Buckling, Shells, Stress, Geometry
Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.
Paper No: NERS-19-1156
https://doi.org/10.1115/1.4048007
Published Online: October 5, 2020
View Article titled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
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Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis
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
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 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