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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

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

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

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

View Article titled, Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

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

Journal Articles

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Wolfgang Hering, Joachim Fuchs, Alexandru Onea, Sara Perez-Martin, Thomas Schaub

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.

Paper No: NERS-21-1031

DOI: https://doi.org/10.1115/1.4052642

Published Online: December 7, 2021

View Article titled, Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation

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

View Article titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

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

Journal Articles

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Haileyesus Tsige-Tamirat, Sara Perez-Martin, Werner Pfrang, Marine Anderhuber, Antoine Gerschenfeld, Laurent Laborde, Konstantin Mikityuk, Christophe Peniguel, Stephane Mimouni

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011305.

Paper No: NERS-20-1117

DOI: https://doi.org/10.1115/1.4051066

Published Online: August 3, 2021

View Article titled, A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Topics: Boiling, Sodium, Sodium fast reactors

Journal Articles

Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Sara Perez-Martin, Marine Anderhuber, Laurent Laborde, Nathalie Girault, Calogera Lombardo, Luca Ammirabile, Konstantin Mikityuk, Stephane Mimouni, Christophe Péniguel, Werner Pfrang

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011310.

Paper No: NERS-21-1049

DOI: https://doi.org/10.1115/1.4050769

Published Online: August 3, 2021

View Article titled, Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Topics: Boiling, Coolants, Flow (Dynamics), Sodium, Sodium fast reactors, Temperature, Temperature profiles, Transients (Dynamics)

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

View Article titled, Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

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

Journal Articles

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Sai Raja Gopal Vadlamudi, Arun K. Nayak

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041109.

Paper No: NERS-19-1165

DOI: https://doi.org/10.1115/1.4048124

Published Online: September 4, 2020

View Article titled, Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Topics: Boiling, Bubbles, Flow (Dynamics), Lift (Fluid dynamics), Lubrication, Porosity, Subcooling, Turbulence, Heat flux

Journal Articles

Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

Sumit V. Prasad, A. K. Nayak

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031301.

Paper No: NERS-19-1043

DOI: https://doi.org/10.1115/1.4044410

Published Online: March 9, 2020

View Article titled, Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

Topics: Boiling, Critical heat flux, Flat plates, Heavy water reactors, Water, Heat, Subcooling

Journal Articles

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

René Manthey, Alexander Knospe, Carsten Lange, Christoph Schuster, Antonio Hurtado

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021103.

Paper No: NERS-18-1135

DOI: https://doi.org/10.1115/1.4044846

Published Online: January 29, 2020

View Article titled, Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

Topics: Pressure, Principal component analysis, Boiling, Stability, Cooling

Journal Articles

In Memoriam: Geoff Hewitt

Michael Bluck, Ph.D., Dr., Igor Pioro, Ph.D., Dr. Tech. Sc., P.Eng.,, Simon Walker, Ph.D., Dr.

ASME J of Nuclear Rad Sci. October 2019, 5(4): 040101.

Paper No: NERS-19-1076

DOI: https://doi.org/10.1115/1.4043661

Published Online: August 2, 2019

View Article titled, In Memoriam: Geoff Hewitt

Topics: Engineering teachers, Engineers, Heat transfer, Multiphase flow, Two-phase flow, Boiling, Design, Heat exchangers

Journal Articles

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041601.

Paper No: NERS-18-1080

DOI: https://doi.org/10.1115/1.4043108

Published Online: July 19, 2019

View Article titled, Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Topics: Accidents, Heat, Heavy water reactors, Temperature, Vessels, Water, Design, Boiling, Nuclear power stations, Failure

Journal Articles

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Sumit V. Prasad, A. K. Nayak

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031014.

Paper No: NERS-17-1062

DOI: https://doi.org/10.1115/1.4039636

Published Online: May 16, 2018

View Article titled, Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Topics: Accidents, Boiling, Heat transfer, Heat transfer coefficients, Heavy water reactors, Temperature, Vessels, Water, Heat, Natural convection

Journal Articles

Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

Shinichiro Uesawa, Yasuo Koizumi, Mitsuhiko Shibata, Hiroyuki Yoshida

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041002.

Paper No: NERS-16-1165

DOI: https://doi.org/10.1115/1.4036987

Published Online: July 31, 2017

View Article titled, Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

Topics: Boiling, Heat transfer, Seas, Seawater, Temperature, Water, Heat flux, Fluids, Nucleate boiling, Bubbles

Journal Articles

Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

Justin H. Spencer

ASME J of Nuclear Rad Sci. April 2017, 3(2): 021008.

Paper No: NERS-16-1075

DOI: https://doi.org/10.1115/1.4035566

Published Online: March 1, 2017

View Article titled, Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

Topics: Boiling, Cavities, Flow visualization, Heat, Heat flux, Vessels, Water, Accidents, Air flow, Porous materials

Journal Articles

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Thambiayah Nitheanandan, X. Cao, J.-H. Choi, D. Dupleac, D.-H. Kim, H. G. Lele, A. K. Nayak, H. P. Rammohan

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020903.

Paper No: NERS-16-1084

DOI: https://doi.org/10.1115/1.4035726

Published Online: March 1, 2017

View Article titled, Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Topics: Accidents, Heat, Vessels, Water, Heavy water reactors, Computers, Pressure, Fuels, Containment, Boilers

Journal Articles

COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Vefa N. Kucukboyaci, Liping Cao, Yixing Sung

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031002.

Paper No: NERS-15-1018

DOI: https://doi.org/10.1115/1.4032594

Published Online: June 17, 2016

View Article titled, COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Topics: Accidents, Coolants, Critical heat flux, Fuel rods, Fuels, Heat transfer, Irradiation (Radiation exposure), Pressurized water reactors, Simulation, Transients (Dynamics)

Journal Articles

Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

Eric C. Forrest, Sarah M. Don, Lin-Wen Hu, Jacopo Buongiorno, Thomas J. McKrell

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021001.

Paper No: NERS-15-1159

DOI: https://doi.org/10.1115/1.4031503

Published Online: February 29, 2016

View Article titled, Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

Topics: Boiling, Bubbles, Flow (Dynamics), Forced convection, Heat flux, Pressure, Temperature, Temperature measurement, Water, Flux (Metallurgy)

Journal Articles

Enhancing Numerical Stability of a Two-Fluid Model by the Use of Interfacial Pressure Terms

Tomio Okawa

ASME J of Nuclear Rad Sci. April 2015, 1(2): 021001.

Paper No: NERS-14-1036

DOI: https://doi.org/10.1115/1.4029415

Published Online: March 24, 2015

View Article titled, Enhancing Numerical Stability of a Two-Fluid Model by the Use of Interfacial Pressure Terms

Topics: Boiling, Flow (Dynamics), Fluids, Numerical stability, Pressure, Subcooling, Two-phase flow, Simulation, Bubbles

Journal citation

NARROW

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

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

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

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

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

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

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

In Memoriam: Geoff Hewitt

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

Enhancing Numerical Stability of a Two-Fluid Model by the Use of Interfacial Pressure Terms

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