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Journal Articles

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.

Paper No: NERS-21-1135

DOI: https://doi.org/10.1115/1.4053827

Published Online: June 15, 2022

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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors

Journal Articles

Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System

Marjan Kromar, Bojan Kurinčič

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041501.

Paper No: NERS-21-1014

DOI: https://doi.org/10.1115/1.4050991

Published Online: March 15, 2022

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Topics: Boron, Cycles, Fuels, Manufacturing, Neutrons, Nuclear design, Nuclear power stations, Nuclear fission, Cross section (Physics), Rods

Journal Articles

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.

Paper No: NERS-21-1015

DOI: https://doi.org/10.1115/1.4051444

Published Online: March 15, 2022

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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons

Journal Articles

Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

Una Baker, Marat Margulis, Eugene Shwageraus, Emil Fridman, Antonio Jiménez Carrascosa, Nuria García Herranz, Oscar Cabellos, Robert Gregg, Jiri Krepel

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011316.

Paper No: NERS-21-1053

DOI: https://doi.org/10.1115/1.4052121

Published Online: September 21, 2021

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Topics: Sodium, Cycles, Simulation

Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haile Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Ben Lindley, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011302.

Paper No: NERS-20-1067

DOI: https://doi.org/10.1115/1.4048765

Published Online: July 20, 2021

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Topics: Cycles, Equilibrium (Physics), Fuels, Modeling, Safety, Sodium fast reactors, Irradiation (Radiation exposure)

Journal Articles

The Environmental, Economic, and Social Performance of Nuclear Technology in Australia

Troy Malatesta

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041202.

Paper No: NERS-20-1089

DOI: https://doi.org/10.1115/1.4049758

Published Online: April 22, 2021

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Topics: Emissions, Fossil fuels, Nuclear power, Climate change, Construction, Cycles, Carbon, Energy generation

Journal Articles

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.

Paper No: NERS-20-1068

DOI: https://doi.org/10.1115/1.4049714

Published Online: April 1, 2021

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Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling

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

Benefits, Drawbacks, and Future Trends of Brayton Helium Gas Turbine Cycles for Gas-Cooled Fast Reactor and Very-High Temperature Reactor Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Emmanuel Osigwe, Pericles Pilidis, Theoklis Nikolaidis, Suresh Sampath, Joao Amaral Teixeira

ASME J of Nuclear Rad Sci. January 2021, 7(1): 014503.

Paper No: NERS-19-1144

DOI: https://doi.org/10.1115/1.4047773

Published Online: October 2, 2020

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Topics: Cycles, Design, Helium, Nuclear power stations, Temperature, Gas turbines, Coolants, Fast neutron reactors

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

Performance Analyses and Evaluation of Co 2 and N 2 as Coolants in a Recuperated Brayton Gas Turbine Cycle for a Generation IV Nuclear Reactor Power Plant

Emmanuel O. Osigwe, Arnold Gad-Briggs, Theoklis Nikolaidis, Pericles Pilidis, Suresh Sampath

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021102.

Paper No: NERS-18-1125

DOI: https://doi.org/10.1115/1.4043589

Published Online: January 29, 2020

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Topics: Carbon dioxide, Compressors, Cycles, Fluids, Power stations, Pressure, Temperature, Design, Turbines, Generation IV reactors

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

William Kyffin, David Gandy, Barry Burdett

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021116.

Paper No: NERS-18-1112

DOI: https://doi.org/10.1115/1.4044752

Published Online: January 29, 2020

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Topics: ASTM International, Fracture toughness, Hot pressing, Manufacturing, Materials properties, Oxygen, Stainless steel, Supply chains, Temperature, Tensile strength

Journal Articles

Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

Emmanuel O. Osigwe, Pericles Pilidis, Theoklis Nikolaidis, Suresh Sampath

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041207.

Paper No: NERS-19-1002

DOI: https://doi.org/10.1115/1.4043681

Published Online: August 2, 2019

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Topics: Closed-cycle gas turbines, Compressors, Computer simulation, Cycles, Design, Engines, Flow (Dynamics), Fluids, Gas turbines, Pressure

Journal Articles

Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis, Theoklis Nikolaidis

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041201.

Paper No: NERS-18-1033

DOI: https://doi.org/10.1115/1.4042116

Published Online: July 19, 2019

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Topics: Cycles, Helium, Nuclear power stations, Temperature, Pressure, Financial risk, Design, Risk, Compressors

Journal Articles

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado

ASME J of Nuclear Rad Sci. April 2019, 5(2): 021004.

Paper No: NERS-16-1070

DOI: https://doi.org/10.1115/1.4041295

Published Online: March 15, 2019

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Topics: Cycles, Irradiation (Radiation exposure), Safety, Temperature, Stress, Heat transfer, Electrical conductance, Steady state, Heat, Cladding systems (Building)

Journal Articles

Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011002.

Paper No: NERS-16-1069

DOI: https://doi.org/10.1115/1.4041269

Published Online: January 24, 2019

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Topics: Heat, Irradiation (Radiation exposure), Safety, Temperature, Manufacturing, Heat transfer, Design, Shrinkage (Materials), Geometry, Cycles

Journal Articles

Analyses of the Costs Associated With Very High Turbine Entry Temperatures in Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

A. Gad-Briggs, P. Pilidis, T. Nikolaidis

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011019.

Paper No: NERS-18-1020

DOI: https://doi.org/10.1115/1.4041276

Published Online: January 24, 2019

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Topics: Compressors, Cooling, Cycles, Helium, Nuclear power stations, Temperature, Turbines, Gas turbines, Pressure, Turbine blades

Journal Articles

Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO 2 as Working Fluid

Marcel Straetz, Joerg Starflinger, Rainer Mertz, Dieter Brillert

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011011.

Paper No: NERS-17-1122

DOI: https://doi.org/10.1115/1.4039884

Published Online: January 24, 2019

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Topics: Cycles, Glass, Heat, Pressure, Pressurized water reactors, Temperature, Turbines, Compressors, Fluids, Supercritical carbon dioxide

Journal Articles

Special Issue: Special Edition ICONE-25

Robert Stakenborghs

ASME J of Nuclear Rad Sci. October 2018, 4(4): 040301.

Paper No: NERS-18-1052

DOI: https://doi.org/10.1115/1.4040963

Published Online: September 10, 2018

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Topics: China, Japan Society of Mechanical Engineers, Nuclear engineering, Nuclear power, Students, Mechanical engineers, Accidents, Computational fluid dynamics, Construction, Cycles

Journal Articles

Analyses of Long-Term Off-Design Performance Strategy and Operation of a High-Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants

A. Gad-Briggs, P. Pilidis, T. Nikolaidis

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041014.

Paper No: NERS-17-1208

DOI: https://doi.org/10.1115/1.4040371

Published Online: September 10, 2018

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Topics: Compressors, Cycles, Design, Flow (Dynamics), Helium, Nuclear power stations, Pressure, Temperature, Turbines, High pressure (Physics)

Journal citation

NARROW

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

The Environmental, Economic, and Social Performance of Nuclear Technology in Australia

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

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

Benefits, Drawbacks, and Future Trends of Brayton Helium Gas Turbine Cycles for Gas-Cooled Fast Reactor and Very-High Temperature Reactor Generation IV Nuclear Power Plants

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

Performance Analyses and Evaluation of Co 2 and N 2 as Coolants in a Recuperated Brayton Gas Turbine Cycle for a Generation IV Nuclear Reactor Power Plant

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

Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production

Analyses of the Costs Associated With Very High Turbine Entry Temperatures in Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO 2 as Working Fluid

Special Issue: Special Edition ICONE-25

Analyses of Long-Term Off-Design Performance Strategy and Operation of a High-Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants

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