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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

Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

R. Andika Putra Dwijayanto, Harun Ardiansyah, Andang Widi Harto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031301.
Paper No: NERS-23-1088
https://doi.org/10.1115/1.4064465
Published Online: April 17, 2024
View Article titled, Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
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Topics: Fluids, Fuels, Geometry, Molten salt reactors, Neutrons, Optimization, Temperature
Journal Articles

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Design Innovation Paper
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
Paper No: NERS-21-1157
https://doi.org/10.1115/1.4054726
Published Online: June 15, 2022
View Article titled, ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
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Topics: Design, Optimization, Safety, Thermal hydraulics, Nuclear design, Nuclear reactors, Computer simulation
Journal Articles

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Emmanuel K. Boafo, Emmanuel Numapau Gyamfi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.
Paper No: NERS-21-1094
https://doi.org/10.1115/1.4053050
Published Online: May 26, 2022
View Article titled, Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA
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Topics: Accidents, Hydrogen, Sensitivity analysis, Uncertainty, Uncertainty quantification, Uncertainty analysis, Design, Optimization
Journal Articles

Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years

Matjaž Žvar, Tomaž Žagar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.
Paper No: NERS-21-1022
https://doi.org/10.1115/1.4052013
Published Online: March 16, 2022
View Article titled, Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years
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Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels
Journal Articles

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Nassar H. S. Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024506.
Paper No: NERS-21-1173
https://doi.org/10.1115/1.4053334
Published Online: February 7, 2022
View Article titled, A Short Inroad to Optimized Compactification of Composite Neutronic Shields
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Topics: Composite materials, Design, Neutrons, Optimization, Neutron beams, Diffusion (Physics), Weight (Mass)
Journal Articles

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011323.
Paper No: NERS-21-1043
https://doi.org/10.1115/1.4052589
Published Online: October 29, 2021
View Article titled, Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
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Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization
Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haileyesus Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011301.
Paper No: NERS-20-1056
https://doi.org/10.1115/1.4048905
Published Online: July 20, 2021
View Article titled, Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results
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Topics: Modeling, Safety, Scram, Sodium, Sodium fast reactors, Temperature, Fuels, Design, Computers, Equilibrium (Physics)
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

Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

Vasilii Volkov, Luka Golibrodo, Alexey Krutikov, Oleg Kudryavtsev, Yurii Nadinskii, Alexander Skibin, Vladimir Sotskov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031403.
Paper No: NERS-19-1162
https://doi.org/10.1115/1.4048234
Published Online: February 19, 2021
View Article titled, Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics
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Topics: Flow (Dynamics), Nozzles, Steam, Evaporation, Boilers, Optimization
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

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Petra Pónya, Gyula Csom, Sándor Fehér
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110.
Paper No: NERS-19-1079
https://doi.org/10.1115/1.4046354
Published Online: June 5, 2020
View Article titled, Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel
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Topics: Coolants, Flow (Dynamics), Irradiation (Radiation exposure), Neutron flux, Neutrons, Reactor vessels, Supercritical water reactors, Design, Fuels, Temperature
Journal Articles

Measuring System for Recuperation Units

Jakub Jiřinec, David Rot
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030908.
Paper No: NERS-18-1120
https://doi.org/10.1115/1.4043103
Published Online: April 16, 2019
View Article titled, Measuring System for Recuperation Units
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Topics: Heat recovery, Optimization, Temperature, Computer software, Control rooms, Measurement systems, Nuclear power stations, Programmable controllers, Space, Suction
Journal Articles

New Exploration on TMSR: Redesign of the TMSR Lattice

J. K. Zhao, S. Y. Si, Q. C. Chen, H. Bei
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011008.
Paper No: NERS-17-1187
https://doi.org/10.1115/1.4041192
Published Online: January 24, 2019
View Article titled, New Exploration on TMSR: Redesign of the TMSR Lattice
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Topics: Design, Fuels, Graphite, Optimization, Molten salt reactors, Neutrons, Cladding systems (Building), Safety
Journal Articles

Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations

F. Salaun, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021003.
Paper No: NERS-17-1010
https://doi.org/10.1115/1.4038557
Published Online: March 5, 2018
View Article titled, Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations
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Topics: Blades, Cycles, Design, Fuels, Optimization, Physics, Supercritical water reactors, Temperature, Thermal hydraulics, Coolants
Journal Articles

Study on Optimization Design for CSR1000 Core

Lianjie Wang, Ping Yang, Di Lu, Wenbo Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011013.
Paper No: NERS-17-1031
https://doi.org/10.1115/1.4037669
Published Online: December 4, 2017
View Article titled, Study on Optimization Design for CSR1000 Core
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Topics: Cycles, Design, Fuels, Optimization, Steady state, Flow (Dynamics), Coolants, Manufacturing
Journal Articles

Novel Genetic Algorithms for Loading Pattern Optimization Using State-of-the-Art Operators and a Simple Test Case

Ella Israeli, Erez Gilad
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 030901.
Paper No: NERS-16-1150
https://doi.org/10.1115/1.4035883
Published Online: May 25, 2017
View Article titled, Novel Genetic Algorithms for Loading Pattern Optimization Using State-of-the-Art Operators and a Simple Test Case
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Topics: Algorithms, Genetic algorithms, Optimization, Probability, Fuels, Pressurized water reactors, Gases
Journal Articles

Optimization of a Multiline Neutron Source Based on a 232 Th Filter

Y. Ben-Galim, R. Moreh, I. Orion
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 030912.
Paper No: NERS-16-1145
https://doi.org/10.1115/1.4036435
Published Online: May 25, 2017
View Article titled, Optimization of a Multiline Neutron Source Based on a 232 Th Filter
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Topics: Filters, Neutron sources, Neutrons, Optimization
Journal Articles

Mass Optimization of a Supercritical CO 2 Brayton Cycle Power Conversion System for a Mars Surface Fission Power Reactor

Kurt E. Harris, Kevin J. Schillo, Yayu M. Hew, Akansha Kumar, Steven D. Howe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031006.
Paper No: NERS-16-1147
https://doi.org/10.1115/1.4035974
Published Online: May 25, 2017
View Article titled, Mass Optimization of a Supercritical CO 2 Brayton Cycle Power Conversion System for a Mars Surface Fission Power Reactor
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Topics: Brayton cycle, Compressors, Cycles, Fluids, Heat exchangers, Nuclear fission, Power conversion systems, Pressure, Supercritical carbon dioxide, Temperature
Journal Articles

Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis

Jia Yang, Rongyong Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014501.
Paper No: NERS-15-1137
https://doi.org/10.1115/1.4035285
Published Online: December 20, 2016
View Article titled, Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis
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Topics: Condensers (steam plant), Cooling, Optimization, Sensitivity analysis, Steam turbines, Design, Nuclear power stations, Tariffs, Cooling towers, Pipes