1-20 of 53
Transients (Dynamics)
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

Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach

Dipanjan Ray, Satya Prakash Saraswat, Vikesh Singh Bhadouria
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041501.
Paper No: NERS-23-1097
https://doi.org/10.1115/1.4065893
Published Online: July 16, 2024
View Article titled, Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
Open the PDF for Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach in another window
Topics: Diffusion (Physics), Fuels, Geometry, Neutron flux, Neutrons, Scalars, Waves, Nuclear fuels, Design, Transients (Dynamics)
Journal Articles

Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant

Ryota Miyake, Shinya Tominaga, Yusuke Terakado, Naoyuki Takado, Toshio Aoki, Chikashi Miyamoto, Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kota Nakata
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2025, 11(1): 011701.
Paper No: NERS-23-1062
https://doi.org/10.1115/1.4064123
Published Online: May 10, 2024
View Article titled, Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant
Open the PDF for Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant in another window
Topics: Artificial intelligence, Nuclear power stations, Power stations, Pumps, Fluctuations (Physics), Signals, Feedwater, Linkages, Time series, Transients (Dynamics)
Journal Articles

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

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. October 2023, 9(4): 041102.
Paper No: NERS-22-1136
https://doi.org/10.1115/1.4056854
Published Online: March 14, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
Open the PDF for Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications in another window
Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)
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
Open the PDF for Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study in another window
Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
Journal Articles

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

Yue Zou, Brian Derreberry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.
Paper No: NERS-21-1040
https://doi.org/10.1115/1.4053013
Published Online: May 26, 2022
View Article titled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities
Open the PDF for Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities in another window
Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification
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
Open the PDF for Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code in another window
Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.
Paper No: NERS-21-1036
https://doi.org/10.1115/1.4050770
Published Online: October 19, 2021
View Article titled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark
Open the PDF for Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark in another window
Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation
Journal Articles

Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

D. Ray, S. P. Saraswat, M. Kumar, O. P. Singh, P. Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021501.
Paper No: NERS-20-1150
https://doi.org/10.1115/1.4049727
Published Online: October 19, 2021
View Article titled, Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
Open the PDF for Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium in another window
Topics: Density, Neutrons, Steady state, Transients (Dynamics), Waves
Journal Articles

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.
Paper No: NERS-20-1202
https://doi.org/10.1115/1.4051875
Published Online: October 19, 2021
View Article titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
Open the PDF for Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water in another window
Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients
Journal Articles

Superphénix Benchmark Part II: Transient Results

A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011321.
Paper No: NERS-21-1052
https://doi.org/10.1115/1.4051877
Published Online: October 8, 2021
View Article titled, Superphénix Benchmark Part II: Transient Results
Open the PDF for Superphénix Benchmark Part II: Transient Results in another window
Topics: Flow (Dynamics), Fuels, Sodium, Temperature, Transients (Dynamics), Modeling
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

Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Sara Perez-Martin, Marine Anderhuber, Laurent Laborde, Nathalie Girault, Calogera Lombardo, Luca Ammirabile, Konstantin Mikityuk, Stephane Mimouni, Christophe Péniguel, Werner Pfrang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011310.
Paper No: NERS-21-1049
https://doi.org/10.1115/1.4050769
Published Online: August 3, 2021
View Article titled, Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments
Open the PDF for Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments in another window
Topics: Boiling, Coolants, Flow (Dynamics), Sodium, Sodium fast reactors, Temperature, Temperature profiles, Transients (Dynamics)
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
Open the PDF for Metallic Fast Reactor Separate Effect Studies for Fuel Safety in another window
Topics: Bubbles, Fuels, Instrumentation, Irradiation (Radiation exposure), Nuclear fission, Safety, Transients (Dynamics), Sodium fast reactors, Testing, Fast neutron reactors
Journal Articles

Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core

Zhigang Li, Ping An, Junjie Pan, Wei Liu, Wei Lu, Shenglong Qiang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034504.
Paper No: NERS-20-1038
https://doi.org/10.1115/1.4048027
Published Online: March 16, 2021
View Article titled, Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core
Open the PDF for Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core in another window
Topics: Dynamics (Mechanics), Fuels, Neutrons, Pressurized water reactors, Spacetime, Temperature, Transients (Dynamics), Water, Cylinders, Computational methods
Journal Articles

Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES

Muhammad Imron, Donny Hartanto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.
Paper No: NERS-20-1064
https://doi.org/10.1115/1.4048764
Published Online: March 16, 2021
View Article titled, Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES
Open the PDF for Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES in another window
Topics: Boron, Coordinate measuring machines, Cross section (Physics), Fuels, Manufacturing, Pressurized water reactors, Transients (Dynamics), Temperature, Diffusion (Physics), Geometry
Journal Articles

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.
Paper No: NERS-20-1157
https://doi.org/10.1115/1.4050207
Published Online: March 10, 2021
View Article titled, Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario
Open the PDF for Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario in another window
Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors
Journal Articles

Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

R. David
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703.
Paper No: NERS-19-1184
https://doi.org/10.1115/1.4048008
Published Online: October 5, 2020
View Article titled, Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria
Open the PDF for Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria in another window
Topics: Accidents, Finite element model, Heat, Melting, Porosity, Temperature, Transients (Dynamics), Uranium, Materials properties
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
Open the PDF for Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks in another window
Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Article titled, A Simplified Two-Group Multipoint Kinetics Model
Open the PDF for A Simplified Two-Group Multipoint Kinetics Model in another window
Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics