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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

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

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

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

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

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.

Paper No: NERS-21-1082

DOI: https://doi.org/10.1115/1.4052590

Published Online: March 15, 2022

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Topics: Computational fluid dynamics, Heat transfer, Stress, Supercritical water reactors, Temperature, Fuels, Small modular reactors

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

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

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.

Paper No: NERS-20-1207

DOI: https://doi.org/10.1115/1.4051612

Published Online: October 19, 2021

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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature

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

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.

Paper No: NERS-20-1204

DOI: https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety

Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.

Paper No: NERS-20-1080

DOI: https://doi.org/10.1115/1.4051723

Published Online: August 12, 2021

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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels

Journal Articles

Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher

Alexandre Lecoanet, Michel Gradeck, Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer, Frédéric Payot, Christophe Journeau, Nicolas Rimbert

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011308.

Paper No: NERS-21-1042

DOI: https://doi.org/10.1115/1.4051448

Published Online: August 3, 2021

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Topics: Ablation (Vaporization technology), Heat transfer, Melting, Sodium fast reactors, Cavities, High temperature, Ice, Design, Temperature, Water

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 Articles

Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

Zayed Ahmed, Seth Eckels, Steven J. Eckels, Hitesh Bindra

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031405.

Paper No: NERS-20-1111

DOI: https://doi.org/10.1115/1.4049280

Published Online: April 2, 2021

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Topics: Boiling, Bubbles, Heat transfer, Heat transfer coefficients, Seawater, Subcooling, Coolants, Wall temperature, Flow (Dynamics), Temperature

Journal Articles

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.

Paper No: NERS-20-1157

DOI: https://doi.org/10.1115/1.4050207

Published Online: March 10, 2021

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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors

Journal Articles

Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications

Radomír Filip, Tomáš Melichar

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021403.

Paper No: NERS-20-1187

DOI: https://doi.org/10.1115/1.4050205

Published Online: March 8, 2021

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Topics: Computational fluid dynamics, Flow (Dynamics), Heat exchangers, Heat transfer, Heat transfer coefficients, Helium, Shells, Temperature, Pressure, Water

Journal Articles

Heat Transfer in Supercritical Fluids: A Review

Kapil Bodkha, N. K. Maheshwari

ASME J of Nuclear Rad Sci. July 2021, 7(3): 030802.

Paper No: NERS-20-1029

DOI: https://doi.org/10.1115/1.4048898

Published Online: February 19, 2021

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Topics: Carbon dioxide, Fluids, Heat transfer, Supercritical fluids, Temperature, Water, Pressure, Heat flux

Journal Articles

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

David Rot, Jan Hrbek, Jakub Jirinec

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602.

Paper No: NERS-20-1147

DOI: https://doi.org/10.1115/1.4048899

Published Online: November 16, 2020

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Topics: Aluminum, Cooling, Design, Electromagnetic induction, Heat transfer, Melting, Temperature, Water, Inductors, Heat flux

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Journal citation

NARROW

Manuscript

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

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

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

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

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

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

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

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

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

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

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher

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

Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications

Heat Transfer in Supercritical Fluids: A Review

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

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