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Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.

Paper No: NERS-21-1158

DOI: https://doi.org/10.1115/1.4056463

Published Online: February 8, 2023

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Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods

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

Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

B. Mikuž, F. Roelofs

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041402.

Paper No: NERS-21-1021

DOI: https://doi.org/10.1115/1.4051446

Published Online: March 22, 2022

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Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Pressure drop, Pressurized water reactors, Temperature, Simulation, Reynolds-averaged Navier–Stokes equations, Turbulence

Journal Articles

Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models

Gustavo D. Pereira, Jian Su

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041604.

Paper No: NERS-20-1104

DOI: https://doi.org/10.1115/1.4049196

Published Online: August 20, 2021

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Topics: Fuels, Heat, Slabs, Temperature, Temperature profiles, Pressurized water reactors, Systems analysis, Fuel rods

Journal Articles

A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating

Bo Liu, Shuisheng He, Charles Moulinec, Juan Uribe

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031111.

Paper No: NERS-19-1080

DOI: https://doi.org/10.1115/1.4046260

Published Online: June 5, 2020

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Topics: Flow (Dynamics), Fuel rods, Turbulence, Water, Buoyancy, Heating, Simulation, Temperature, Heat transfer, Computational fluid dynamics

Journal Articles

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Attila Kiss, Bence Mervay

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107.

Paper No: NERS-19-1069

DOI: https://doi.org/10.1115/1.4046842

Published Online: June 5, 2020

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Topics: Flow (Dynamics), Fuel rods, Geometry, Wire, Wall temperature, Fuels, Corners (Structural elements), Temperature

Journal Articles

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Attila Kiss, Béla Hegyesi, Patrik Richárd Ujváry, András Szabolcs Ványi, Gyula Csom

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108.

Paper No: NERS-19-1070

DOI: https://doi.org/10.1115/1.4046904

Published Online: June 5, 2020

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Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire

Journal Articles

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Yuiko Motome, Yoshiya Akiyama, Hiroyuki Murao

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021115.

Paper No: NERS-19-1073

DOI: https://doi.org/10.1115/1.4045075

Published Online: February 3, 2020

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Topics: Earthquakes, Fuel rods, Fuel storage, Fuels, Radiation (Physics), Safety, Spent fuel storage, Tsunamis, Nuclear fission, Shapes

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

Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid

Ganesh Lal Kumawat, Anuj Kumar Kansal, Naresh Kumar Maheshwari, Avaneesh Sharma

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041301.

Paper No: NERS-18-1042

DOI: https://doi.org/10.1115/1.4042120

Published Online: July 19, 2019

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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Simulation, Turbulence

Journal Articles

Rod Bow Ultrasonic Measurements Possibilities

Marcin Kopeć, Martina Malá

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030901.

Paper No: NERS-18-1044

DOI: https://doi.org/10.1115/1.4041277

Published Online: April 16, 2019

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Topics: Fuel rods, Probes, Inspection, Ultrasonic measurement, Fuels, Radiation (Physics), Nuclear fuels

Journal Articles

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Felix Boldt

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.

Paper No: NERS-18-1065

DOI: https://doi.org/10.1115/1.4042118

Published Online: March 15, 2019

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Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation

Journal Articles

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Martín Lemes, Alicia Denis, Alejandro Soba

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020903.

Paper No: NERS-18-1078

DOI: https://doi.org/10.1115/1.4042705

Published Online: March 15, 2019

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Topics: Accidents, Cladding systems (Building), Coolants, Fuel rods, Fuels, High temperature, Hydrogen, Simulation, Temperature, Water

Journal Articles

Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium

Koichi Hata, Katsuya Fukuda, Tohru Mizuuchi

ASME J of Nuclear Rad Sci. April 2019, 5(2): 021002.

Paper No: NERS-17-1088

DOI: https://doi.org/10.1115/1.4042356

Published Online: March 15, 2019

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Topics: Cylinders, Fuel rods, Heat transfer, Natural convection, Sodium, Temperature

Journal Articles

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Zhang Donghui, Xiong Wenbin, Li Huwei, Wu Mingyu, Wang Xinzhe

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041018.

Paper No: NERS-17-1272

DOI: https://doi.org/10.1115/1.4040029

Published Online: September 10, 2018

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Topics: China, Fast neutron reactors, Fuels, Manufacturing, Fuel rods, Isotopes, Heat transfer, Failure, Cladding systems (Building), Design

Journal Articles

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

Wang Zhu, Zhang Chungyu, Yuan Cenxi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031008.

Paper No: NERS-17-1103

DOI: https://doi.org/10.1115/1.4039848

Published Online: May 16, 2018

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Topics: Cladding systems (Building), Fuel rods, Fuels, Modeling, Nuclear fission, Temperature, Pressurized water reactors, Stress, Accidents

Journal Articles

Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures

Hussam A. M. Zahlan, Laurence K. H. Leung, Yan-Ping Huang, Guang-Xu Liu

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011004.

Paper No: NERS-17-1050

DOI: https://doi.org/10.1115/1.4037720

Published Online: December 4, 2017

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Topics: Carbon dioxide, Databases, Flow (Dynamics), Fluids, Fuel rods, Water, Heat transfer, Uncertainty, Annulus

Journal Articles

Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

Krishna Podila, Yanfei Rao

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011008.

Paper No: NERS-17-1027

DOI: https://doi.org/10.1115/1.4037747

Published Online: December 4, 2017

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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Pressure, Simulation, Turbulence, Water, Wire, Temperature

Journal Articles

Numerical Simulation Research on the Performance of SCWR Fuel Rod

Changbing Tang, Shuo Xing, Hua Pang, Ping Chen, Yi Zhou

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011014.

Paper No: NERS-17-1029

DOI: https://doi.org/10.1115/1.4038060

Published Online: December 4, 2017

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Topics: Cladding systems (Building), Computer simulation, Fuel rods, Fuels, Irradiation (Radiation exposure), Stainless steel, Supercritical water reactors, Temperature, Thermal expansion, Thermal conductivity

Journal Articles

Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

Malwina Gradecka, Roman Thiele, Henryk Anglart

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031015.

Paper No: NERS-15-1087

DOI: https://doi.org/10.1115/1.4032635

Published Online: June 17, 2016

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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Rods, Temperature, Water, Geometry, Boundary-value problems, Fluids

Journal citation

NARROW

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

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

Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models

A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid

Rod Bow Ultrasonic Measurements Possibilities

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures

Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

Numerical Simulation Research on the Performance of SCWR Fuel Rod

Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

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