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Journal Articles

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031404.

Paper No: NERS-22-1052

DOI: https://doi.org/10.1115/1.4055932

Published Online: February 8, 2023

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Topics: Bubbles, Bubbly flow, Fluids, Pressure, Simulation, Plumes (Fluid dynamics), Porosity, Surface tension, Flow (Dynamics), Two-phase flow

Journal Articles

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Rolando Calabrese

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041603.

Paper No: NERS-21-1027

DOI: https://doi.org/10.1115/1.4054941

Published Online: September 1, 2022

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Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling

Journal Articles

Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

Chenguang Li, Krishna Podila, Blair P. Bromley, Yanfei Rao

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011402.

Paper No: NERS-22-1028

DOI: https://doi.org/10.1115/1.4054943

Published Online: July 19, 2022

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Topics: Computational fluid dynamics, Fuels, Modeling, Pressure, Pressurized water reactors, Manufacturing, Flow (Dynamics), Small modular reactors

Journal Articles

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.

Paper No: NERS-21-1118

DOI: https://doi.org/10.1115/1.4054079

Published Online: May 26, 2022

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Topics: Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature

Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.

Paper No: NERS-21-1101

DOI: https://doi.org/10.1115/1.4053049

Published Online: March 22, 2022

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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing

Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.

Paper No: NERS-21-1030

DOI: https://doi.org/10.1115/1.4052519

Published Online: March 22, 2022

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Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress

Journal Articles

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection

Claude Jamond, Elena Martin Lopez, Xue-Nong Chen, Nathalie Girault, Pierre Gubernatis, Andrei Rineiski

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011325.

Paper No: NERS-20-1142

DOI: https://doi.org/10.1115/1.4052489

Published Online: December 14, 2021

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Topics: Fuels, Heat transfer, Modeling, Natural convection, Heat, Temperature, Flux (Metallurgy)

Journal Articles

Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator

Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010305.

Paper No: NERS-21-1121

DOI: https://doi.org/10.1115/1.4052641

Published Online: December 14, 2021

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Topics: Safety, Sodium, Sodium fast reactors, Modeling

Journal Articles

Superphénix Benchmark Part II: Transient Results

A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011321.

Paper No: NERS-21-1052

DOI: https://doi.org/10.1115/1.4051877

Published Online: October 8, 2021

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Topics: Flow (Dynamics), Fuels, Sodium, Temperature, Transients (Dynamics), Modeling

Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Alexander Ponomarev, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.

Paper No: NERS-20-1186

DOI: https://doi.org/10.1115/1.4051514

Published Online: September 13, 2021

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Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat

Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haile Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Ben Lindley, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011302.

Paper No: NERS-20-1067

DOI: https://doi.org/10.1115/1.4048765

Published Online: July 20, 2021

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Topics: Cycles, Equilibrium (Physics), Fuels, Modeling, Safety, Sodium fast reactors, Irradiation (Radiation exposure)

Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haileyesus Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011301.

Paper No: NERS-20-1056

DOI: https://doi.org/10.1115/1.4048905

Published Online: July 20, 2021

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Topics: Modeling, Safety, Scram, Sodium, Sodium fast reactors, Temperature, Fuels, Design, Computers, Equilibrium (Physics)

Journal Articles

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.

Paper No: NERS-20-1068

DOI: https://doi.org/10.1115/1.4049714

Published Online: April 1, 2021

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Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling

Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.

Paper No: NERS-20-1012

DOI: https://doi.org/10.1115/1.4048477

Published Online: March 16, 2021

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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors

Journal Articles

The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

Lian-Cheng Wang, Matthew H. Kaye

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011601.

Paper No: NERS-19-1094

DOI: https://doi.org/10.1115/1.4046784

Published Online: October 1, 2020

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Topics: Nuclear fuels, Phase diagrams, Temperature, Uranium, Modeling, Military systems, Nuclear fission, Spent nuclear fuels

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

A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids

Andrew W. Copping, Metin I. Yaras

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031112.

Paper No: NERS-19-1081

DOI: https://doi.org/10.1115/1.4046654

Published Online: June 5, 2020

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Topics: Buoyancy, Flow (Dynamics), Heat transfer, Modeling, Turbulence

Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.

Paper No: NERS-19-1083

DOI: https://doi.org/10.1115/1.4046843

Published Online: June 5, 2020

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Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling

Journal Articles

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

T. Beuthe, A. Vasić, H. Zahlan, A. Nava Domínguez

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115.

Paper No: NERS-20-1002

DOI: https://doi.org/10.1115/1.4047288

Published Online: June 5, 2020

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Topics: Heat transfer, Modeling, Pressure, Supercritical water reactors, Temperature, Simulation, Accidents, Testing, Water, Transients (Dynamics)

Journal Articles

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

Mithil Parekh, Yuan Gao, Mariana Jockenhoevel-Barttfeld, Karl Waedt

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031802.

Paper No: NERS-17-1277

DOI: https://doi.org/10.1115/1.4046262

Published Online: May 5, 2020

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Topics: Computer software, Failure, Instrumentation, Modeling, Nuclear power stations, Safety, Control systems, Hardware, Three-dimensional modeling

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Journal citation

NARROW

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection

Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator

Superphénix Benchmark Part II: Transient Results

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

A Simplified Two-Group Multipoint Kinetics Model

A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

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