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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

The Transfer of Xenon-135 to Molten Salt Reactor Graphite

Terry Price, Ondrej Chvala
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041001.
Paper No: NERS-22-1113
https://doi.org/10.1115/1.4064464
Published Online: June 21, 2024
View Article titled, The Transfer of Xenon-135 to Molten Salt Reactor Graphite
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Topics: Graphite, Porosity, Fuels, Molten salt reactors, Mass transfer, Diffusion (Physics)
Journal Articles

Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors

Li Wanai, Gong Helin, Zhang Chunyu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031503.
Paper No: NERS-21-1114
https://doi.org/10.1115/1.4055379
Published Online: February 22, 2023
View Article titled, Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors
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Topics: Diffusion (Physics), Finite element methods, Neutron flux, Neutrons, Computation, Finite element model
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

Thermal Soil Radon Mitigation

Francisco J. Arias, Salvador De Las Heras
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024503.
Paper No: NERS-20-1215
https://doi.org/10.1115/1.4050832
Published Online: October 19, 2021
View Article titled, Thermal Soil Radon Mitigation
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Topics: Diffusion (Physics), Soil, Temperature, Rocks, Temperature gradient
Journal Articles

Canonical Implementation of Simplified Spherical Harmonics (SP L ) in the Neutron Diffusion Code AZNHEX

Guillermo Muñoz-Peña, Edmundo del Valle Gallegos, Armando Gomez-Torres
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031502.
Paper No: NERS-20-1114
https://doi.org/10.1115/1.4049277
Published Online: April 16, 2021
View Article titled, Canonical Implementation of Simplified Spherical Harmonics (SP L ) in the Neutron Diffusion Code AZNHEX
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Topics: Approximation, Diffusion (Physics), Neutrons
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

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Yong Lu, Zheng Jiang, Linyang Li, Cuiping Wang, Yihui Guo, Jiajia Han, Xingjun Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605.
Paper No: NERS-19-1151
https://doi.org/10.1115/1.4047718
Published Online: October 5, 2020
View Article titled, Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation
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Topics: Diffusion (Physics), Irradiation (Radiation exposure), Phase diagrams, Zirconium
Journal Articles

Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

Andrew Oussoren, Paul Chan, Diane Wowk, Andrew Prudil
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604.
Paper No: NERS-19-1018
https://doi.org/10.1115/1.4048120
Published Online: October 5, 2020
View Article titled, Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths
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Topics: Failure, Fracture (Materials), Fuels, Nuclear fission, Diffusion (Physics)
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
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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics
Journal Articles

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.
Paper No: NERS-19-1161
https://doi.org/10.1115/1.4047113
Published Online: September 4, 2020
View Article titled, ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors
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Topics: Design, Diffusion (Physics), Heat exchangers, High temperature, Reliability, Testing, Construction, ASME Standards, ASME Boiler and Pressure Vessel Code, Stress
Journal Articles

Xenon Behavior in Molten Salt Reactor Graphite

Terry J. Price, Ondrej Chvala, Zack Taylor
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041303.
Paper No: NERS-19-1115
https://doi.org/10.1115/1.4046356
Published Online: June 3, 2020
View Article titled, Xenon Behavior in Molten Salt Reactor Graphite
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Topics: Graphite, Molten salt reactors, Diffusion (Physics), Mass transfer
Journal Articles

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

M. D. Tucker, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401.
Paper No: NERS-19-1065
https://doi.org/10.1115/1.4045485
Published Online: March 9, 2020
View Article titled, The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors
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Topics: Algorithms, Cross section (Physics), Feedback, Fuels, Simulation, Uncertainty, Uncertainty analysis, Uranium, Physics, Diffusion (Physics)
Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.
Paper No: NERS-19-1046
https://doi.org/10.1115/1.4044751
Published Online: November 8, 2019
View Article titled, Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
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Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient
Journal Articles

Application of Stiffness Confinement Method in Transient Transport Calculation

Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011107.
Paper No: NERS-19-1033
https://doi.org/10.1115/1.4044749
Published Online: November 8, 2019
View Article titled, Application of Stiffness Confinement Method in Transient Transport Calculation
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Topics: Density, Neutrons, Stiffness, Transients (Dynamics), Diffusion (Physics)
Journal Articles

A Study of Superhomogenization Applied to PHWR Lattices

Thomas A. Ferguson, Eleodor M. Nichita
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011109.
Paper No: NERS-19-1049
https://doi.org/10.1115/1.4044748
Published Online: November 8, 2019
View Article titled, A Study of Superhomogenization Applied to PHWR Lattices
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Topics: Fuels, Heavy water reactors, Light water reactors, Water, Diffusion (Physics), Cross section (Physics)
Journal Articles

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Terry J. Price, Ondrej Chvala, Zack Taylor
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041210.
Paper No: NERS-18-1087
https://doi.org/10.1115/1.4043813
Published Online: September 3, 2019
View Article titled, Molten Salt Reactor Xenon Analysis: Review and Decomposition
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Topics: Fuels, Graphite, Mass transfer, Molten salt reactors, Bubbles, Diffusion (Physics)
Journal Articles

An Analytical Solution for the Two-Group Diffusion Theory Analysis of Multiregion Source-Driven Systems

Huseyin Atilla Ozgener, Ceyhun Yavuz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031401.
Paper No: NERS-17-1302
https://doi.org/10.1115/1.4042021
Published Online: May 3, 2019
View Article titled, An Analytical Solution for the Two-Group Diffusion Theory Analysis of Multiregion Source-Driven Systems
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Topics: Diffusion (Physics), Polishing equipment, Neutron sources, Neutrons, Design
Journal Articles

Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR

Tetsuaki Takeda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021003.
Paper No: NERS-17-1288
https://doi.org/10.1115/1.4041690
Published Online: March 15, 2019
View Article titled, Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR
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Topics: Gases, High temperature, Natural convection, Numerical analysis, Temperature, Diffusion (Physics), Flow (Dynamics), Very high temperature reactors, Low temperature, Fluids
Journal Articles

A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide

Qiang Zhao, Zheng Zhang, Xiaoping Ouyang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2018, 4(3): 034503.
Paper No: NERS-17-1278
https://doi.org/10.1115/1.4039885
Published Online: May 16, 2018
View Article titled, A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide
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Topics: Atoms, Density functional theory, Diffusion (Physics), Nuclear fission, Uranium, Elasticity, Fuels, Oxygen