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Journal Articles

An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition

Mingfu He, Minghui Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031401.
Paper No: NERS-23-1093
https://doi.org/10.1115/1.4064337
Published Online: April 17, 2024
View Article titled, An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition
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Topics: Bubbles, Dynamics (Mechanics), Heat flux, Heat transfer, Nucleate boiling, Pool boiling, Boiling, Nucleation (Physics), Quenching (Metalworking), Critical heat flux
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021403.
Paper No: NERS-21-1164
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.
Paper No: NERS-21-1149
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.
Paper No: NERS-21-1031
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)
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.
Paper No: NERS-20-1202
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
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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

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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011310.
Paper No: NERS-21-1049
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
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Topics: Boiling, Coolants, Flow (Dynamics), Sodium, Sodium fast reactors, Temperature, Temperature profiles, Transients (Dynamics)
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011305.
Paper No: NERS-20-1117
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
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Topics: Boiling, Sodium, Sodium fast reactors
Journal Articles

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

Zayed Ahmed, Seth Eckels, Steven J. Eckels, Hitesh Bindra
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031405.
Paper No: NERS-20-1111
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041109.
Paper No: NERS-19-1165
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031301.
Paper No: NERS-19-1043
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
Open the PDF for Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs in another window
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021103.
Paper No: NERS-18-1135
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
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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.
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: In Memoriam
ASME J of Nuclear Rad Sci. October 2019, 5(4): 040101.
Paper No: NERS-19-1076
https://doi.org/10.1115/1.4043661
Published Online: August 2, 2019
View Article titled, In Memoriam: Geoff Hewitt
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041601.
Paper No: NERS-18-1080
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031014.
Paper No: NERS-17-1062
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041002.
Paper No: NERS-16-1165
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
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Topics: Boiling, Heat transfer, Seas, Seawater, Temperature, Water, Heat flux, Fluids, Nucleate boiling, Bubbles
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020903.
Paper No: NERS-16-1084
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
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Topics: Accidents, Heat, Vessels, Water, Heavy water reactors, Computers, Pressure, Fuels, Containment, Boilers
Journal Articles

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

Justin H. Spencer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021008.
Paper No: NERS-16-1075
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
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Topics: Boiling, Cavities, Flow visualization, Heat, Heat flux, Vessels, Water, Accidents, Air flow, Porous materials
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031002.
Paper No: NERS-15-1018
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021001.
Paper No: NERS-15-1159
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021001.
Paper No: NERS-14-1036
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
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Topics: Boiling, Flow (Dynamics), Fluids, Numerical stability, Pressure, Subcooling, Two-phase flow, Simulation, Bubbles