Volume 6 Issue 1 | ASME J. of Nuclear Rad Sci.

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Editorial

Igor L. Pioro

ASME J of Nuclear Rad Sci. January 2020, 6(1): 010201. doi: https://doi.org/10.1115/1.4045356

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Topics: China , Nuclear engineering , Nuclear power , Radiation (Physics) , Electricity (Physics) , Safety

Reviewer's Recognition

ASME J of Nuclear Rad Sci. January 2020, 6(1): 010202. doi: https://doi.org/10.1115/1.4045123

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Guest Editorial

ASME-NED Chair's Message

Shripad T. Revankar

ASME J of Nuclear Rad Sci. January 2020, 6(1): 010301. doi: https://doi.org/10.1115/1.4045235

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Topics: Career development , Education , Engineers , Mechanical engineers , Nuclear engineering , Nuclear power , Radiation (Physics) , Students , Renewable energy , Maintenance

Greetings From JSME and the Report on ICONE27

Tomio Okawa

ASME J of Nuclear Rad Sci. January 2020, 6(1): 010302. doi: https://doi.org/10.1115/1.4045120

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View articletitled, Greetings From JSME and the Report on ICONE27

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Topics: Japan Society of Mechanical Engineers , Nuclear engineering

Professor Masahiro Kawaji on His 65th Birthday

Mohamed M. Awad, Sanjoy Banerjee, Vijay K. Dhir, Paolo Di Marco, Satish G. Kandlikar, Michael Kauffeld, Masahiro Shoji, John R. Thome

ASME J of Nuclear Rad Sci. January 2020, 6(1): 010303. doi: https://doi.org/10.1115/1.4045033

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Topics: Engineering teachers

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

Adriaan Buijs, Ph.D., Eleodor Nichita, Ph.D., PEng.

ASME J of Nuclear Rad Sci. January 2020, 6(1): 010304. doi: https://doi.org/10.1115/1.4045355

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View articletitled, Special Section: CNS's 8th International Conference on Simulation Methods in Nuclear Science and Engineering

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Topics: Simulation

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

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

L. Y. Huang, H. Z. Fan, M. Maltchevski, A. Ranger

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011101. doi: https://doi.org/10.1115/1.4044459

Abstract

View articletitled, 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

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

Z. Zheng, R. Li, Y. Zhou, Q. Mei, L. Deng

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011102. doi: https://doi.org/10.1115/1.4045030

Abstract

View articletitled, 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

Theoretical Development of Cross Section Uncertainty Library for Core Simulators

Dongli Huang, Hany S. Abdel-Khalik

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011103. doi: https://doi.org/10.1115/1.4045031

Abstract

View articletitled, Theoretical Development of Cross Section Uncertainty Library for Core Simulators

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Topics: Physics , Uncertainty , Simulation

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

Dongli Huang, Hany S. Abdel-Khalik

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011104. doi: https://doi.org/10.1115/1.4045032

Abstract

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

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Topics: Uncertainty

Multiscale Mesoscale Modeling of Porosity Evolution in Oxide Fuels

M. J. Welland, K. D. Colins, N. Ofori-Opoku, A. A. Prudil, E. S. Thomas

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011105. doi: https://doi.org/10.1115/1.4044405

Abstract

View articletitled, 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

Estimation of Flow-Accelerated Corrosion Rate in Nuclear Piping System

Indranil Hazra, Mahesh D. Pandey, Mikko I. Jyrkama

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011106. doi: https://doi.org/10.1115/1.4044407

Abstract

View articletitled, 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

Application of Stiffness Confinement Method in Transient Transport Calculation

Chuntao Tang

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011107. doi: https://doi.org/10.1115/1.4044749

Abstract

View articletitled, Application of Stiffness Confinement Method in Transient Transport Calculation

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

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108. doi: https://doi.org/10.1115/1.4044751

Abstract

View articletitled, 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

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

Abstract

View articletitled, 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)

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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011110. doi: https://doi.org/10.1115/1.4044747

Abstract

View articletitled, 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

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

Kevin (Wenhai) Li, Michel Gaudet

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011111. doi: https://doi.org/10.1115/1.4045124

Abstract

View articletitled, 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

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

L. Sun, K. Podila, Q. Chen, A. M. Bayomy, Y. F. Rao

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011112. doi: https://doi.org/10.1115/1.4044531

Abstract

View articletitled, 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

Research Papers

General

Simulation of the Performance of the Venturi Scrubber for an Advanced Reactor Containment Venting Conditions

Goel Paridhi, K. Nayak Arun

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011201. doi: https://doi.org/10.1115/1.4044845

Abstract

View articletitled, Simulation of the Performance of the Venturi Scrubber for an Advanced Reactor Containment Venting Conditions

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Topics: Absorption , Containment , Drops , Pressure , Venturi tubes

A Review of Molten Salt Reactor Xenon Analysis Literature

T. J. Price, O. Chvala

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011202. doi: https://doi.org/10.1115/1.4044746

Abstract

View articletitled, A Review of Molten Salt Reactor Xenon Analysis Literature

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Topics: Molten salt reactors , Graphite , Bubbles , Mass transfer , Fuels , Porosity

Next Generation/Advanced Reactors

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301. doi: https://doi.org/10.1115/1.4044847

Abstract

View articletitled, RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

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Topics: Coolants , Flow (Dynamics) , Modeling , Pipes , Pumps , Sodium , Temperature , Transients (Dynamics) , Vessels , Three-dimensional models

Thermal Hydraulics and CFD

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401. doi: https://doi.org/10.1115/1.4045125

Abstract

View articletitled, Experimental Investigation on Flash Evaporation Related to Pipe Leakage

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Topics: Evaporation , Flow (Dynamics) , High temperature , Leakage , Pipes , Pressure , Sensors , Sprays , Temperature , Temperature distribution

Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing

Massimo Sarotto, Gabriele Firpo, Anatoly Kochetkov, Antonin Krása, Emil Fridman, Jerzy Cetnar, Grazyna Domanska

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011402. doi: https://doi.org/10.1115/1.4044000

Abstract

View articletitled, Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing

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Topics: Design , Fast neutron reactors , Nuclear fission , Nuclides , Uncertainty , Uncertainty analysis , Licensing , Neutrons , Rods , Simulation

Nuclear Fuels/Cycles and Materials

In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Sumit V. Prasad, P. P. Kulkarni, D. C. Yadav, P. K. Verma, A. K. Nayak

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011601. doi: https://doi.org/10.1115/1.4043999

Abstract

View articletitled, In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

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Topics: Temperature , Vessels , Heat transfer , Heavy water reactors

Plant Systems, O&M, and Life Cycle

Application of a Graded Approach to Support the National Research Universal Reactor U-2 Experimental Loop Return to Service

M. Karam

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011801. doi: https://doi.org/10.1115/1.4044750

Abstract

View articletitled, Application of a Graded Approach to Support the National Research Universal Reactor U-2 Experimental Loop Return to Service

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Topics: Accidents , Design , Earthquakes , Safety , Pressure , Fuels , Failure , Hazards , Heat

RAW Management and Decommissioning

Radiographic Nondestructive Testing Simulations Using gate Software Toolkit

Eslam Taha, M. S. Mohammed, Essam Banoqitah

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011901. doi: https://doi.org/10.1115/1.4044909

Abstract

View articletitled, Radiographic Nondestructive Testing Simulations Using <span class="small-caps">gate</span> Software Toolkit

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Topics: Computer software , Gates (Closures) , Nondestructive evaluation , Radiation (Physics) , Simulation , Testing , Wedges , X-rays , Gamma rays , Emissions

Technology Reviews

The Autoignition of Nuclear Reactor Power Plant Explosions

Robert A. Leishear

ASME J of Nuclear Rad Sci. January 2020, 6(1): 014001. doi: https://doi.org/10.1115/1.4044807

Abstract

View articletitled, The Autoignition of Nuclear Reactor Power Plant Explosions

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Topics: Explosions , Hydrogen

Issues

Editorial

Guest Editorial

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

Research Papers

General

Next Generation/Advanced Reactors

Thermal Hydraulics and CFD

Nuclear Fuels/Cycles and Materials

Plant Systems, O&M, and Life Cycle

RAW Management and Decommissioning

Technology Reviews

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