1-20 of 26
Rods
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3

Jacob Yankey, Marisa Monreal, Matt Jackson, Michael Simpson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030906.
Paper No: NERS-23-1066
https://doi.org/10.1115/1.4064598
Published Online: March 8, 2024
View Article titled, Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3
Open the PDF for Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3 in another window
Topics: Circuits, Electrodes, Molten salt reactors, Temperature, Zirconium, Electrodeposition, Rods, Electrons
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
Open the PDF for Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor in another window
Topics: Control systems, Design, Fast neutron reactors, Fuels, Neutrons, Rods, Coolants, Boron, Absorption, Safety
Journal Articles

Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly

Md. Tanvir Ahmed, Afroza Shelley, Md. Nobir Hosen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021602.
Paper No: NERS-23-1069
https://doi.org/10.1115/1.4063757
Published Online: January 29, 2024
View Article titled, Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly
Open the PDF for Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly in another window
Topics: Cycles, Fuel rods, Fuels, Manufacturing, Neutron flux, Neutrons, Nuclear fission, Nuclear fuel cycle, Rods, Safety
Journal Articles

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Lorenzo Loi, Stefano Lorenzi, Antonio Cammi, Carolina Introini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014502.
Paper No: NERS-23-1029
https://doi.org/10.1115/1.4064308
Published Online: December 22, 2023
View Article titled, A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
Open the PDF for A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset in another window
Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Nuclides, Simulation, Temperature, Uncertainty, Geometry, Errors
Journal Articles

Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 2023
View Article titled, Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
Open the PDF for Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor in another window
Topics: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics
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
Open the PDF for Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code in another window
Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041501.
Paper No: NERS-21-1014
https://doi.org/10.1115/1.4050991
Published Online: March 15, 2022
View Article titled, 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
Open the PDF for 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 in another window
Topics: Boron, Cycles, Fuels, Manufacturing, Neutrons, Nuclear design, Nuclear power stations, Nuclear fission, Cross section (Physics), Rods
Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.
Paper No: NERS-21-1046
https://doi.org/10.1115/1.4051449
Published Online: October 8, 2021
View Article titled, Superphénix Benchmark Part I: Results of Static Neutronics
Open the PDF for Superphénix Benchmark Part I: Results of Static Neutronics in another window
Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics
Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Alexander Ponomarev, 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): 011313.
Paper No: NERS-20-1186
https://doi.org/10.1115/1.4051514
Published Online: September 13, 2021
View Article titled, Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor
Open the PDF for Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor in another window
Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat
Journal Articles

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

Evaldas Bubelis, Michael Schikorr, 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): 011309.
Paper No: NERS-21-1048
https://doi.org/10.1115/1.4050563
Published Online: August 3, 2021
View Article titled, Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor
Open the PDF for Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor in another window
Topics: Rods, Sodium fast reactors, Transients (Dynamics), Cooling, Circuits, Flow (Dynamics)
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
Open the PDF for Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing in another window
Topics: Design, Fast neutron reactors, Nuclear fission, Nuclides, Uncertainty, Uncertainty analysis, Licensing, Neutrons, Rods, Simulation
Journal Articles

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

Xiong Wenbin, Cao Jian, Huang Chaoyun, Bie Yewang, Wang Yanqi, Li Jufeng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031018.
Paper No: NERS-17-1132
https://doi.org/10.1115/1.4039596
Published Online: May 16, 2018
View Article titled, Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model
Open the PDF for Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model in another window
Topics: Design, Fuels, Rods, Manufacturing, Nuclear power stations, Modeling, Boron, Physics
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
Open the PDF for Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP in another window
Topics: China, Fast neutron reactors, Safety, Design, Rods
Journal Articles

Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure

Thomas Schulenberg, Hongbo Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011005.
Paper No: NERS-17-1026
https://doi.org/10.1115/1.4038061
Published Online: December 4, 2017
View Article titled, Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure
Open the PDF for Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure in another window
Topics: Heat transfer, Pressure, Supercritical water reactors, Temperature, Transient heat transfer, Fuels, Film boiling, Rods, Heat flux, Transients (Dynamics)
Journal Articles

Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load

Emiliya Georgieva, Yavor Dinkov, Kostadin Ivanov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031005.
Paper No: NERS-16-1132
https://doi.org/10.1115/1.4035550
Published Online: May 25, 2017
View Article titled, Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load
Open the PDF for Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load in another window
Topics: Coolants, Flow (Dynamics), Fuels, Manufacturing, Pressure, Simulation, Steam, Stress, Temperature, Transients (Dynamics)
Journal Articles

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011005.
Paper No: NERS-15-1226
https://doi.org/10.1115/1.4033813
Published Online: December 20, 2016
View Article titled, Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor
Open the PDF for Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor in another window
Topics: High temperature, Neutron flux, Rods, Fuels, Design, Temperature, Computational methods
Journal Articles

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.
Paper No: NERS-16-1007
https://doi.org/10.1115/1.4034478
Published Online: December 20, 2016
View Article titled, A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
Open the PDF for A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor in another window
Topics: Heat flux, Nucleate boiling, Pressurized water reactors, Rods, Safety, Scram, Spacetime, Thermal hydraulics, Transients (Dynamics), Temperature profiles
Journal Articles

Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Kaichao Sun, Lin-Wen Hu, Charles Forsberg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031003.
Paper No: NERS-15-1184
https://doi.org/10.1115/1.4032873
Published Online: June 17, 2016
View Article titled, Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor
Open the PDF for Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor in another window
Topics: Coolants, Design, Fuels, Nuclear fuel cycle, Safety, Rods, Particulate matter, Control systems, High temperature
Journal Articles

Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

Malwina Gradecka, Roman Thiele, Henryk Anglart
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031015.
Paper No: NERS-15-1087
https://doi.org/10.1115/1.4032635
Published Online: June 17, 2016
View Article titled, Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers
Open the PDF for Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Rods, Temperature, Water, Geometry, Boundary-value problems, Fluids
Journal Articles

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

Alberto Sartori, Antonio Cammi, Lelio Luzzi, Gianluigi Rozza
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021019.
Paper No: NERS-14-1062
https://doi.org/10.1115/1.4031945
Published Online: February 29, 2016
View Article titled, A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods
Open the PDF for A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods in another window
Topics: Eigenvalues, Errors, Modeling, Neutron flux, Nuclear reactors, Rods, Shapes, Approximation, Neutrons, Diffusion (Physics)