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Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.

Paper No: NERS-22-1136

DOI: https://doi.org/10.1115/1.4056854

Published Online: March 14, 2023

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Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)

Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor with SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1145

DOI: https://doi.org/10.1115/1.4062119

Published Online: March 11, 2023

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Topics: Additive manufacturing, Fuels, Particulate matter, Design, Geometry, Coolants, Heat transfer, Computational fluid dynamics, Computer software, Discrete element methods

Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.

Paper No: NERS-21-1161

DOI: https://doi.org/10.1115/1.4056834

Published Online: March 2, 2023

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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)

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

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.

Paper No: NERS-22-1020

DOI: https://doi.org/10.1115/1.4056239

Published Online: February 8, 2023

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Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection

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

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

Markus Petroff, Rudi Kulenovic, Jörg Starflinger

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041702.

Paper No: NERS-21-1028

DOI: https://doi.org/10.1115/1.4051876

Published Online: September 3, 2022

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Topics: Floods, Particulate matter, Quenching (Metalworking), Temperature, Test facilities, Water, Flow (Dynamics), Concretes

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

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

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

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.

Paper No: NERS-21-1149

DOI: https://doi.org/10.1115/1.4053828

Published Online: June 1, 2022

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Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water

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

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Yue Zou, Brian Derreberry

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.

Paper No: NERS-21-1040

DOI: https://doi.org/10.1115/1.4053013

Published Online: May 26, 2022

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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification

Journal Articles

Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

Sal Rodriguez, Nima Fathi, Mahyar Pourghasemi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034502.

Paper No: NERS-20-1213

DOI: https://doi.org/10.1115/1.4054342

Published Online: May 26, 2022

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Topics: Flow (Dynamics), Internal flow, Kinematics, Turbulence, Viscosity, Simulation, Eddies (Fluid dynamics)

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

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)

2 3 4 5

Journal citation

NARROW

Manuscript

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor with SiC Matrix and TRISO Particle Fuel

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

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

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

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

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

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

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

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

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

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

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

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

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

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