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Special Section: CNS's 8th International Conference on Simulation Methods in Nuclear Science and Engineering
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Journal Articles

Estimation of Flow-Accelerated Corrosion Rate in Nuclear Piping System

Indranil Hazra, Mahesh D. Pandey, Mikko I. Jyrkama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011106.
Paper No: NERS-19-1032
https://doi.org/10.1115/1.4044407
Published Online: November 25, 2019
View Article titled, Estimation of Flow-Accelerated Corrosion Rate in Nuclear Piping System
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Topics: Algorithms, Chain, Computation, Corrosion, Density, Flow (Dynamics), Parameter estimation, Pipes, Piping systems, Wall thickness
Journal Articles

Fueling Machine Model for Simulation of Spent Fuel Behavior in Postulated Fuel Handling Accidents

L. Y. Huang, H. Z. Fan, M. Maltchevski, A. Ranger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011101.
Paper No: NERS-18-1119
https://doi.org/10.1115/1.4044459
Published Online: November 8, 2019
View Article titled, Fueling Machine Model for Simulation of Spent Fuel Behavior in Postulated Fuel Handling Accidents
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Topics: Fuels, Machinery, Spent nuclear fuels, Simulation, Coolants, Accidents
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 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

Theoretical Development of Cross Section Uncertainty Library for Core Simulators

Dongli Huang, Hany S. Abdel-Khalik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011103.
Paper No: NERS-18-1133
https://doi.org/10.1115/1.4045031
Published Online: November 8, 2019
View Article titled, Theoretical Development of Cross Section Uncertainty Library for Core Simulators
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Topics: Physics, Uncertainty, Simulation
Journal Articles

Multiscale Mesoscale Modeling of Porosity Evolution in Oxide Fuels

M. J. Welland, K. D. Colins, N. Ofori-Opoku, A. A. Prudil, E. S. Thomas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011105.
Paper No: NERS-19-1019
https://doi.org/10.1115/1.4044405
Published Online: November 8, 2019
View Article titled, Multiscale Mesoscale Modeling of Porosity Evolution in Oxide Fuels
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Topics: Bubbles, Fuels, Grain boundaries, Irradiation (Radiation exposure), Modeling, Nuclear fission, Percolation theory, Porosity, Crystals, Tunnels
Journal Articles

Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow

Shawn Somers-Neal, Vien Nguyen, Edgar Matida, Vinh Tang, Tarik Kaya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011110.
Paper No: NERS-19-1050
https://doi.org/10.1115/1.4044747
Published Online: November 8, 2019
View Article titled, Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow
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Topics: Pipes, Reynolds number, Solidification, Temperature, Turbulence, Thermal conductivity, Flow (Dynamics), Simulation, Pipe flow, Freezing
Journal Articles

Computational Fluid Dynamics Modeling of Fire and Human Evacuation for Nuclear Applications

L. Sun, K. Podila, Q. Chen, A. M. Bayomy, Y. F. Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011112.
Paper No: NERS-19-1071
https://doi.org/10.1115/1.4044531
Published Online: November 8, 2019
View Article titled, Computational Fluid Dynamics Modeling of Fire and Human Evacuation for Nuclear Applications
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Topics: Evacuations, Fire, Simulation, Computational fluid dynamics, Smoke, Vents, Modeling
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

Application of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems

Dongli Huang, Hany S. Abdel-Khalik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011104.
Paper No: NERS-18-1134
https://doi.org/10.1115/1.4045032
Published Online: November 8, 2019
View Article titled, Application of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems
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Topics: Uncertainty
Journal Articles

High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor

Kevin (Wenhai) Li, Michel Gaudet
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011111.
Paper No: NERS-19-1056
https://doi.org/10.1115/1.4045124
Published Online: November 8, 2019
View Article titled, High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor
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Topics: Concretes, Diffraction gratings, Fiber optic sensors, Fibers, Fracture (Materials), Resolution (Optics), Sensors, Wavelength, Fiber Bragg gratings, Concrete beams