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Journal Articles

Long-Term Performance of Semimetallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das

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

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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

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.

Paper No: NERS-21-1156

DOI: https://doi.org/10.1115/1.4054546

Published Online: June 15, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.

Paper No: NERS-20-1206

DOI: https://doi.org/10.1115/1.4053689

Published Online: May 26, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.

Paper No: NERS-21-1100

DOI: https://doi.org/10.1115/1.4052808

Published Online: May 26, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.

Paper No: NERS-21-1040

DOI: https://doi.org/10.1115/1.4053013

Published Online: May 26, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.

Paper No: NERS-21-1087

DOI: https://doi.org/10.1115/1.4054557

Published Online: May 17, 2022

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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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.

Paper No: NERS-21-1030

DOI: https://doi.org/10.1115/1.4052519

Published Online: March 22, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.

Paper No: NERS-21-1082

DOI: https://doi.org/10.1115/1.4052590

Published Online: March 15, 2022

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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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021302.

Paper No: NERS-20-1185

DOI: https://doi.org/10.1115/1.4050421

Published Online: October 19, 2021

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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

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041901.

Paper No: NERS-20-1091

DOI: https://doi.org/10.1115/1.4050296

Published Online: April 22, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031303.

Paper No: NERS-20-1051

DOI: https://doi.org/10.1115/1.4048896

Published Online: March 16, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031301.

Paper No: NERS-19-1139

DOI: https://doi.org/10.1115/1.4048903

Published Online: February 19, 2021

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Topics: Closed-cycle gas turbines, Compressors, Control systems, Cycles, Fluids, Pressure, Storage tanks, Stress, Temperature, Valves

Journal Articles

Mechanical Tests Results of Laser Shock Peening-Treated Austenitic Steel

Zbyněk Špirit, Jan Kaufman, Michal Chocholoušek, Josef Strejcius

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024506.

Paper No: NERS-20-1135

DOI: https://doi.org/10.1115/1.4048766

Published Online: November 16, 2020

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Topics: Fatigue life, Laser hardening, Lasers, Shock (Mechanics), Shot peening, Stainless steel, Steel, Mechanical testing, Stress, Pressure

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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024505.

Paper No: NERS-20-1113

DOI: https://doi.org/10.1115/1.4048900

Published Online: November 16, 2020

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Topics: Creep, Rupture, Steel, Particulate matter, Stress, Grain size, Heat treating (Metalworking), Grain boundaries, Etching, Heat

Journal Articles

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

Ashok Kumar, Anindya Chatterjee

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011801.

Paper No: NERS-20-1001

DOI: https://doi.org/10.1115/1.4047494

Published Online: October 5, 2020

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.

Paper No: NERS-19-1156

DOI: https://doi.org/10.1115/1.4048007

Published Online: October 5, 2020

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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

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

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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

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Emmanuel O. Osigwe, Arnold Gad-Briggs, Dodeye Igbong, Theoklis Nikolaidis, Pericles Pilidis

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021201.

Paper No: NERS-19-1042

DOI: https://doi.org/10.1115/1.4044260

Published Online: February 24, 2020

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Topics: Cycles, Pressure, Stress, Temperature, Flow (Dynamics), Compressors, Power stations, Heat, Modeling, Closed-cycle gas turbines

Journal Articles

Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities

K. A. Joshi, B. Poudel, R. Gokaraju

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021801.

Paper No: NERS-19-1026

DOI: https://doi.org/10.1115/1.4045122

Published Online: February 24, 2020

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Topics: Distributed power generation, Energy storage, Small modular reactors, Stress, Generators, Modeling

Journal Articles

Leakage Estimate in Nonuniformly Compressed Packing Rings

Ali Salah Omar Aweimer, Abdel-Hakim Bouzid, Zijian Zhao

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021114.

Paper No: NERS-19-1061

DOI: https://doi.org/10.1115/1.4045225

Published Online: February 5, 2020

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Topics: Leakage, Packing (Shipments), Packings (Cushioning), Stress, Compression, Pressure, Valves, Porosity, Helium

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Journal citation

NARROW

Long-Term Performance of Semimetallic Gaskets

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

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

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

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

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

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

A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

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

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

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

Mechanical Tests Results of Laser Shock Peening-Treated Austenitic Steel

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

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

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

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

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities

Leakage Estimate in Nonuniformly Compressed Packing Rings

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