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Journal Articles

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

Li Wanai, Gong Helin, Zhang Chunyu

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031503.

Paper No: NERS-21-1114

DOI: https://doi.org/10.1115/1.4055379

Published Online: February 22, 2023

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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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024506.

Paper No: NERS-21-1173

DOI: https://doi.org/10.1115/1.4053334

Published Online: February 7, 2022

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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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024503.

Paper No: NERS-20-1215

DOI: https://doi.org/10.1115/1.4050832

Published Online: October 19, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031502.

Paper No: NERS-20-1114

DOI: https://doi.org/10.1115/1.4049277

Published Online: April 16, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.

Paper No: NERS-20-1064

DOI: https://doi.org/10.1115/1.4048764

Published Online: March 16, 2021

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605.

Paper No: NERS-19-1151

DOI: https://doi.org/10.1115/1.4047718

Published Online: October 5, 2020

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604.

Paper No: NERS-19-1018

DOI: https://doi.org/10.1115/1.4048120

Published Online: October 5, 2020

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.

Paper No: NERS-19-1155

DOI: https://doi.org/10.1115/1.4046254

Published Online: October 1, 2020

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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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.

Paper No: NERS-19-1161

DOI: https://doi.org/10.1115/1.4047113

Published Online: September 4, 2020

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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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041303.

Paper No: NERS-19-1115

DOI: https://doi.org/10.1115/1.4046356

Published Online: June 3, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401.

Paper No: NERS-19-1065

DOI: https://doi.org/10.1115/1.4045485

Published Online: March 9, 2020

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Topics: Algorithms, Cross section (Physics), Feedback, Fuels, Simulation, Uncertainty, Uncertainty analysis, Uranium, Physics, Diffusion (Physics)

Journal Articles

A Study of Superhomogenization Applied to PHWR Lattices

Thomas A. Ferguson, Eleodor M. Nichita

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011109.

Paper No: NERS-19-1049

DOI: https://doi.org/10.1115/1.4044748

Published Online: November 8, 2019

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Topics: Fuels, Heavy water reactors, Light water reactors, Water, Diffusion (Physics), Cross section (Physics)

Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.

Paper No: NERS-19-1046

DOI: https://doi.org/10.1115/1.4044751

Published Online: November 8, 2019

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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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011107.

Paper No: NERS-19-1033

DOI: https://doi.org/10.1115/1.4044749

Published Online: November 8, 2019

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Topics: Density, Neutrons, Stiffness, Transients (Dynamics), Diffusion (Physics)

Journal Articles

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Terry J. Price, Ondrej Chvala, Zack Taylor

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041210.

Paper No: NERS-18-1087

DOI: https://doi.org/10.1115/1.4043813

Published Online: September 3, 2019

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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

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031401.

Paper No: NERS-17-1302

DOI: https://doi.org/10.1115/1.4042021

Published Online: May 3, 2019

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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

ASME J of Nuclear Rad Sci. April 2019, 5(2): 021003.

Paper No: NERS-17-1288

DOI: https://doi.org/10.1115/1.4041690

Published Online: March 15, 2019

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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

ASME J of Nuclear Rad Sci. July 2018, 4(3): 034503.

Paper No: NERS-17-1278

DOI: https://doi.org/10.1115/1.4039885

Published Online: May 16, 2018

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Topics: Atoms, Density functional theory, Diffusion (Physics), Nuclear fission, Uranium, Elasticity, Fuels, Oxygen

Journal Articles

The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021008.

Paper No: NERS-17-1079

DOI: https://doi.org/10.1115/1.4038653

Published Online: March 5, 2018

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Topics: Deformation, Diffusion (Physics), Eigenvalues, Neutron flux, Neutrons, Polynomials, Currents, Computational methods, Physics, Nuclear engineering

Journal Articles

Cesium and Strontium Immobilization in Portland Cement Pastes Blended With Pozzolanic Additives

Gabriela Bar-Nes, Yael Peled, Zorik Shamish, Amnon Katz

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030907.

Paper No: NERS-16-1061

DOI: https://doi.org/10.1115/1.4035415

Published Online: May 25, 2017

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Topics: Cements (Adhesives), Diffusion (Physics), Ions, Slag cement, Strontium, Thermal analysis

Journal citation

NARROW

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

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Thermal Soil Radon Mitigation

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

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

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

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

A Simplified Two-Group Multipoint Kinetics Model

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

Xenon Behavior in Molten Salt Reactor Graphite

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

A Study of Superhomogenization Applied to PHWR Lattices

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

Application of Stiffness Confinement Method in Transient Transport Calculation

Molten Salt Reactor Xenon Analysis: Review and Decomposition

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

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

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

The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Cesium and Strontium Immobilization in Portland Cement Pastes Blended With Pozzolanic Additives

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