1-20 of 35
Geometry
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

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Available to Purchase
Accepted Manuscript
Zhenyu Wang, Xian Zhang, Shichang Liu, Rui Che, Yixue Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1095
https://doi.org/10.1115/1.4068167
Published Online: March 13, 2025
View Articletitled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
Open the PDF for Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC in another window
Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Journal Articles

Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation

Available to Purchase
Mohammad Khan, Jehad Haque, Saad Islam, Lubon Putul, Mehedi Hasan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031401.
Paper No: NERS-24-1060
https://doi.org/10.1115/1.4067628
Published Online: February 14, 2025
View Articletitled, Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation
Open the PDF for Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Pipe bends, Pipes, Pressure, Supercritical water reactors, Turbulence, Water, Geometry, Fluids
Journal Articles

Investigation of thermal cut-off energy for accurate analysis of High Temperature Engineering Test Reactor

Free
Accepted Manuscript
Satoshi Takeda, Takanori Kitada, Akio Yamamoto, Kazuya Yamaji, Hiroki Koike, Koji Asano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1108
https://doi.org/10.1115/1.4067755
Published Online: January 28, 2025
View Articletitled, Investigation of thermal cut-off energy for accurate analysis of High Temperature Engineering Test Reactor
Open the PDF for Investigation of thermal cut-off energy for accurate analysis of High Temperature Engineering Test Reactor in another window
Topics: High temperature, Resonance, Electromagnetic scattering, Fuels, Radiation scattering, Scattering (Physics), Errors, Geometry, Neutrons, Temperature
Journal Articles

Uniform thermal expansion reactivity evaluation based on reactivity coefficient for sodium-cooled fast reactor

Free
Accepted Manuscript
Satoshi Takeda, Takanori Kitada, Takafumi Okita, Eiji Hoashi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1089
https://doi.org/10.1115/1.4067483
Published Online: December 21, 2024
View Articletitled, Uniform thermal expansion reactivity evaluation based on reactivity coefficient for sodium-cooled fast reactor
Open the PDF for Uniform thermal expansion reactivity evaluation based on reactivity coefficient for sodium-cooled fast reactor in another window
Topics: Sodium fast reactors, Thermal expansion, Fuels, Cladding systems (Building), Geometry, Shapes
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

Available to Purchase
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 Articletitled, 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

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

Available to Purchase
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 Articletitled, Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
Open the PDF for Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume in another window
Topics: Fluids, Fuels, Geometry, Molten salt reactors, Neutrons, Optimization, Temperature
Journal Articles

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

Available to Purchase
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 Articletitled, 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

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Available to Purchase
Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Articletitled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
Open the PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel in another window
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Journal Articles

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

Available to Purchase
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 Articletitled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
Open the PDF for ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code in another window
Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Available to Purchase
Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-Pueng, Yanin Sukjai
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.
Paper No: NERS-21-1156
https://doi.org/10.1115/1.4054546
Published Online: June 15, 2022
View Articletitled, The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)
Open the PDF for The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE) in another window
Topics: Airfoils, Flow (Dynamics), Geometry, Stress, Heat exchangers, Heat transfer, Temperature, Fluids, Structural analysis
Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Available to Purchase
Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
https://doi.org/10.1115/1.4051612
Published Online: October 19, 2021
View Articletitled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
Open the PDF for Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs in another window
Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature
Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Available to Purchase
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 Articletitled, 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

Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Available to Purchase
Hubert Delacroix, Frédéric Navacchia
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011317.
Paper No: NERS-20-1066
https://doi.org/10.1115/1.4052376
Published Online: October 4, 2021
View Articletitled, Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing
Open the PDF for Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing in another window
Topics: Evacuations, Flow (Dynamics), Flowmeters, Jets, Pipes, Sodium, Eddies (Fluid dynamics), Eddy currents (Electricity), Geometry, Design
Journal Articles

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Available to Purchase
Janos Bodi, 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): 011307.
Paper No: NERS-20-1183
https://doi.org/10.1115/1.4050417
Published Online: August 3, 2021
View Articletitled, Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor
Open the PDF for Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor in another window
Topics: Deformation, Displacement, Finite element analysis, Geometry, Manufacturing, Sodium fast reactors, Fuels, Simulation, Absorption
Journal Articles

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

Available to Purchase
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 Articletitled, 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

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Available to Purchase
Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.
Paper No: NERS-20-1009
https://doi.org/10.1115/1.4047495
Published Online: October 5, 2020
View Articletitled, Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
Open the PDF for Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment in another window
Topics: Boundary-value problems, Computational fluid dynamics, Coolants, Flow (Dynamics), Geometry, Temperature, Cooling, Temperature distribution, Metals
Journal Articles

Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR

Available to Purchase
Ashok Kumar, Anindya Chatterjee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011801.
Paper No: NERS-20-1001
https://doi.org/10.1115/1.4047494
Published Online: October 5, 2020
View Articletitled, Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR
Open the PDF for Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR in another window
Topics: Buckling, Shells, Stress, Geometry
Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Available to Purchase
Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.
Paper No: NERS-19-1168
https://doi.org/10.1115/1.4047441
Published Online: September 4, 2020
View Articletitled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
Open the PDF for Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves
Journal Articles

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Available to Purchase
Attila Kiss, Bence Mervay
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107.
Paper No: NERS-19-1069
https://doi.org/10.1115/1.4046842
Published Online: June 5, 2020
View Articletitled, Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle
Open the PDF for Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle in another window
Topics: Flow (Dynamics), Fuel rods, Geometry, Wire, Wall temperature, Fuels, Corners (Structural elements), Temperature
Journal Articles

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

Available to Purchase
Damian E. Ramajo, Santiago F. Corzo, Norberto M. Nigro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021202.
Paper No: NERS-19-1039
https://doi.org/10.1115/1.4045121
Published Online: February 24, 2020
View Articletitled, Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors
Open the PDF for Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors in another window
Topics: Flow (Dynamics), Fluids, Pipes, Pressure, Simulation, Water, Computational fluid dynamics, Geometry, Drainage, Computer simulation