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Journal Articles

Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS

Accepted Manuscript
Raj Kumar Singh, Deb Mukhopadhyay, Devang Khakhar, J. B. Joshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1004
https://doi.org/10.1115/1.4066001
Published Online: July 20, 2024
View Article titled, Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS
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Topics: Pressurized water reactors, Turbulence, Computational fluid dynamics, Design, Computer simulation, Dynamics (Mechanics), Equilibrium (Physics), Fuels, Geometry, Momentum
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
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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

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

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
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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

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

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

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

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

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

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
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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

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

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

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

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

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 Article titled, Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
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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

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 Article titled, Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR
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Topics: Buckling, Shells, Stress, Geometry
Journal Articles

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

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

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

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 Article titled, Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors
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Topics: Flow (Dynamics), Fluids, Pipes, Pressure, Simulation, Water, Computational fluid dynamics, Geometry, Drainage, Computer simulation
Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.
Paper No: NERS-19-1024
https://doi.org/10.1115/1.4045035
Published Online: February 24, 2020
View Article titled, Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality
Journal Articles

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

Z. Zheng, R. Li, Y. Zhou, Q. Mei, L. Deng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011102.
Paper No: NERS-18-1130
https://doi.org/10.1115/1.4045030
Published Online: November 8, 2019
View Article titled, A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette
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Topics: Computers, Errors, Fluence (Radiation measurement), Geometry, Neutrons, Particulate matter, Phase space, Photons, Weight (Mass), Dosimeters
Journal Articles

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

I. K. Baidoo, J. Zou, B. Li, J. Song, B. Wu, Q. Yang, Z. Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041402.
Paper No: NERS-18-1123
https://doi.org/10.1115/1.4043100
Published Online: July 19, 2019
View Article titled, Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments
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Topics: Atoms, Displacement, Dosimetry, Fluence (Radiation measurement), Fuels, Geometry, Iron, Manufacturing, Modeling, Neutron flux