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Journal Articles

Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

Qingqing Liu, Julio Diaz, Victor Petrov, Adam Burak, Annalisa Manera, Joseph Kelly, Xiaodong Sun

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021403.

Paper No: NERS-21-1164

DOI: https://doi.org/10.1115/1.4055002

Published Online: September 2, 2022

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Topics: Boiling, Densitometers, Flow (Dynamics), Porosity, X-rays, Water, Flow visualization, Two-phase flow, Instrumentation, Wall temperature

Journal Articles

Experimental Evaluation of Two-Phase Heat Transfer Coefficient Under Oscillatory Flow Conditions and Correlation Development

Rakesh Kumar, Dinesh K. Chandraker, Arnab Dasgupta, Arun K. Nayak

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011403.

Paper No: NERS-21-1186

DOI: https://doi.org/10.1115/1.4055090

Published Online: September 2, 2022

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Topics: Flow (Dynamics), Heat transfer coefficients, Oscillations

Journal Articles

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401.

Paper No: NERS-22-1006

DOI: https://doi.org/10.1115/1.4054842

Published Online: July 19, 2022

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Topics: Flow (Dynamics), Steam, Temperature, Turbulence, Condensation, Flat plates, Boundary layer turbulence, Computational fluid dynamics, Computation

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

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-Pueng, Yanin Sukjai

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.

Paper No: NERS-21-1156

DOI: https://doi.org/10.1115/1.4054546

Published Online: June 15, 2022

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Topics: Airfoils, Flow (Dynamics), Geometry, Stress, Heat exchangers, Heat transfer, Temperature, Fluids, Structural analysis

Journal Articles

Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Abdullah G. Weiss, Laith J. Zaidan, Mohammad T. H. Bani Ahmad, M. Gomaa Abdoelatef, John W. Peterson, Alexander D. Lindsay, Fande Kong, Karim Ahmed, Mark L. Kimber

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.

Paper No: NERS-21-1170

DOI: https://doi.org/10.1115/1.4054685

Published Online: June 15, 2022

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Topics: Computational fluid dynamics, Cylinders, Errors, Finite element analysis, Flow (Dynamics), Pressure, Simulation, Vortex street, Engineering simulation, Physics

Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.

Paper No: NERS-21-1073

DOI: https://doi.org/10.1115/1.4052014

Published Online: May 26, 2022

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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics

Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402.

Paper No: NERS-21-1068

DOI: https://doi.org/10.1115/1.4052807

Published Online: May 26, 2022

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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results

Journal Articles

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Michio Murase, Yoichi Utanohara, Akio Tomiyama

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404.

Paper No: NERS-21-1097

DOI: https://doi.org/10.1115/1.4053051

Published Online: May 26, 2022

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Topics: Condensation, Heat transfer, Steam, Temperature, Temperature distribution, Computational fluid dynamics, Mass transfer, Flat plates

Journal Articles

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Ganesh V, Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031401.

Paper No: NERS-21-1060

DOI: https://doi.org/10.1115/1.4053220

Published Online: May 26, 2022

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Topics: Floods, Temperature, Vessels, Water

Journal Articles

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

S. P. Chauhan, D. K. Chandraker, Naveen Kumar

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031405.

Paper No: NERS-21-1106

DOI: https://doi.org/10.1115/1.4053221

Published Online: May 26, 2022

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Topics: Excitation, Thermal stratification, Water, Temperature gradient, Temperature, Heat

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

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.

Paper No: NERS-21-1012

DOI: https://doi.org/10.1115/1.4051515

Published Online: March 22, 2022

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Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)

Journal Articles

Hybrid Nodal Integral/Finite Element Method for Time-Dependent Convection Diffusion Equation

Sundar Namala, Rizwan Uddin

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021406.

Paper No: NERS-21-1066

DOI: https://doi.org/10.1115/1.4051928

Published Online: January 12, 2022

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Topics: Finite element methods

Journal Articles

Investigation of Critical Heat Flux for Plutonium-Based Mixed Oxide Advanced Fuel Bundle Design

Lan Qin Yuan, Jun Yang, Bruce Addicott, Matthew Dickerson, Vinson Gauthier

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021405.

Paper No: NERS-21-1054

DOI: https://doi.org/10.1115/1.4052521

Published Online: January 12, 2022

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Topics: Critical heat flux, Fuels, Pressure, Flow (Dynamics)

Journal Articles

Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube

Dong Yang, Jiaxiang Chen, Yongchang Feng, Lin Chen

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021402.

Paper No: NERS-20-1194

DOI: https://doi.org/10.1115/1.4051248

Published Online: October 19, 2021

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Topics: Heat transfer, Turbulence, Water, Temperature, Computer simulation, Heat flux, Heat, Density, Flow (Dynamics), Viscosity

Journal Articles

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.

Paper No: NERS-20-1202

DOI: https://doi.org/10.1115/1.4051875

Published Online: October 19, 2021

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Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients

Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021401.

Paper No: NERS-20-1182

DOI: https://doi.org/10.1115/1.4050209

Published Online: October 19, 2021

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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results

Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.

Paper No: NERS-21-1036

DOI: https://doi.org/10.1115/1.4050770

Published Online: October 19, 2021

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Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation

Journal Articles

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.

Paper No: NERS-20-1021

DOI: https://doi.org/10.1115/1.4050211

Published Online: April 16, 2021

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Topics: Condensation, Cooling, Design, Flow (Dynamics), Heat transfer, Steam, Test facilities, Temperature, Pressure, Water

Journal citation

NARROW

Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

Experimental Evaluation of Two-Phase Heat Transfer Coefficient Under Oscillatory Flow Conditions and Correlation Development

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

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

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

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

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Hybrid Nodal Integral/Finite Element Method for Time-Dependent Convection Diffusion Equation

Investigation of Critical Heat Flux for Plutonium-Based Mixed Oxide Advanced Fuel Bundle Design

Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

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