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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

Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes

Bikash Pattanayak, Hardik B. Kothadia
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041402.
Paper No: NERS-23-1008
https://doi.org/10.1115/1.4063041
Published Online: September 15, 2023
View Article titled, Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes
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Topics: Bubbles, Critical heat flux, Dimensions, Pool boiling
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021405.
Paper No: NERS-21-1054
https://doi.org/10.1115/1.4052521
Published Online: January 12, 2022
View Article titled, Investigation of Critical Heat Flux for Plutonium-Based Mixed Oxide Advanced Fuel Bundle Design
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Topics: Critical heat flux, Fuels, Pressure, Flow (Dynamics)
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

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

Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction

Yuzhou Chen, Minfu Zhao, Keming Bi, Bin Yang, Dongxu Zhang, Kaiwen Du
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011006.
Paper No: NERS-17-1048
https://doi.org/10.1115/1.4038215
Published Online: December 4, 2017
View Article titled, Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction
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Topics: Critical heat flux, Pressure, Water, Subcooling
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)