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Journal Articles

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Thanh Mai Vu, Le Quang Linh Tran, Thi Hong Bui, Nhu Viet Ha Pham
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031501.
Paper No: NERS-23-1039
https://doi.org/10.1115/1.4064780
Published Online: April 17, 2024
View Article titled, Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries
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Topics: Eigenvalues, Fast neutron reactors, Neutrons, Nuclear fission, Nuclear reactors, Uncertainty, Uncertainty analysis, Cross section (Physics), Electromagnetic scattering, Radiation scattering
Journal Articles

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021503.
Paper No: NERS-23-1046
https://doi.org/10.1115/1.4063739
Published Online: January 29, 2024
View Article titled, Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
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Topics: Control systems, Design, Fast neutron reactors, Fuels, Neutrons, Rods, Coolants, Boron, Absorption, Safety
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
Paper No: NERS-22-1165
https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Article titled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
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Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.
Paper No: NERS-21-1161
https://doi.org/10.1115/1.4056834
Published Online: March 2, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
Journal Articles

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

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
https://doi.org/10.1115/1.4053827
Published Online: June 15, 2022
View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors
Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, 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): 041401.
Paper No: NERS-21-1012
https://doi.org/10.1115/1.4051515
Published Online: March 22, 2022
View Article titled, Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code
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Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
Journal Articles

Small Modular Reactors: Learning From the Past

Esam M. A. Hussein
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034508.
Paper No: NERS-20-1152
https://doi.org/10.1115/1.4050478
Published Online: May 26, 2021
View Article titled, Small Modular Reactors: Learning From the Past
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Topics: Coolants, Fast neutron reactors, Fuels, Gas cooled reactors, High temperature, Liquid metals, Molten salt reactors, Pressurized water reactors, Small modular reactors, Licensing
Journal Articles

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

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 Article titled, 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

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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.
Paper No: NERS-20-1068
https://doi.org/10.1115/1.4049714
Published Online: April 1, 2021
View Article titled, Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor
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Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2021, 7(1): 014503.
Paper No: NERS-19-1144
https://doi.org/10.1115/1.4047773
Published Online: October 2, 2020
View Article titled, 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
Open the PDF for 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 in another window
Topics: Cycles, Design, Helium, Nuclear power stations, Temperature, Gas turbines, Coolants, Fast neutron reactors
Journal Articles

Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing

Massimo Sarotto, Gabriele Firpo, Anatoly Kochetkov, Antonin Krása, Emil Fridman, Jerzy Cetnar, Grazyna Domanska
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011402.
Paper No: NERS-18-1132
https://doi.org/10.1115/1.4044000
Published Online: November 29, 2019
View Article titled, Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing
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Topics: Design, Fast neutron reactors, Nuclear fission, Nuclides, Uncertainty, Uncertainty analysis, Licensing, Neutrons, Rods, Simulation
Journal Articles

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.
Paper No: NERS-19-1001
https://doi.org/10.1115/1.4044847
Published Online: November 29, 2019
View Article titled, RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test
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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models
Journal Articles

RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant

Accepted Manuscript
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-16-1130
https://doi.org/10.1115/1.4036986
Published Online: April 30, 2019
View Article titled, RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant
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Topics: Coolants, Eutectic alloys, Fast neutron reactors, Simulation
Journal Articles

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Zhang Donghui, Xiong Wenbin, Li Huwei, Wu Mingyu, Wang Xinzhe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041018.
Paper No: NERS-17-1272
https://doi.org/10.1115/1.4040029
Published Online: September 10, 2018
View Article titled, Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
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Topics: China, Fast neutron reactors, Fuels, Manufacturing, Fuel rods, Isotopes, Heat transfer, Failure, Cladding systems (Building), Design
Journal Articles

Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

Xiong Wenbin, Xie Qin, Li Huwei, Yang Sengai, Mao Huan, Cao Jian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2018, 4(2): 024501.
Paper No: NERS-17-1105
https://doi.org/10.1115/1.4038999
Published Online: March 5, 2018
View Article titled, Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP
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Topics: China, Fast neutron reactors, Safety, Design, Rods
Journal Articles

Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water

Sukarman, Akifumi Yamaji, Takayuki Someya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011012.
Paper No: NERS-17-1033
https://doi.org/10.1115/1.4037719
Published Online: December 4, 2017
View Article titled, Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
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Topics: Coolants, Design, Fuels, Manufacturing, Pressure, Water, Fast neutron reactors, Power density
Journal Articles

Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Luigi Lepore, Romolo Remetti
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041018.
Paper No: NERS-17-1017
https://doi.org/10.1115/1.4037262
Published Online: July 31, 2017
View Article titled, Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs
Open the PDF for Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs in another window
Topics: Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Neutrons, Sensors, Signals, Simulation, Instrumentation
Journal Articles

Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor

Wenzhong Zhou, Rong Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041007.
Paper No: NERS-15-1020
https://doi.org/10.1115/1.4031033
Published Online: September 3, 2015
View Article titled, Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor
Open the PDF for Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor in another window
Topics: Fuels, Light water reactors, Oxygen, Simulation, Temperature, Fast neutron reactors, Diffusion (Physics), Heat, Boundary-value problems, Thermal diffusion
Journal Articles

Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031004.
Paper No: NERS-14-1027
https://doi.org/10.1115/1.4029521
Published Online: May 20, 2015
View Article titled, Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
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Topics: Cross section (Physics), Density, Flux (Metallurgy), Fuels, Nuclides, Spectra (Spectroscopy), Nuclear fission, Fast neutron reactors
Journal Articles

A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor

S. Lorenzi, A. Cammi, L. Luzzi, R. Ponciroli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031007.
Paper No: NERS-14-1050
https://doi.org/10.1115/1.4029791
Published Online: May 20, 2015
View Article titled, A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor
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Topics: Diffusion (Physics), Eigenfunctions, Fast neutron reactors, Fuels, Modeling, Simulation, Temperature, Transients (Dynamics), Neutron flux, Neutrons