1-9 of 9
Subcooling
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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
Open the PDF for Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water in another window
Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients
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
Open the PDF for Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant in another window
Topics: Boiling, Bubbles, Heat transfer, Heat transfer coefficients, Seawater, Subcooling, Coolants, Wall temperature, Flow (Dynamics), Temperature
Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.
Paper No: NERS-20-1012
https://doi.org/10.1115/1.4048477
Published Online: March 16, 2021
View Article titled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
Open the PDF for Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage in another window
Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors
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
Open the PDF for Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling in another window
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

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
Open the PDF for Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction in another window
Topics: Critical heat flux, Pressure, Water, Subcooling
Journal Articles

Computational Fluid Dynamics Simulation of Direct-Contact Condensation Phenomenon of Vapor Jet in Subcooled Water Tank

Yu Ji, Hao-Chun Zhang, Yi-Ning Zhang, Xu-Wei Wang, Yan Quan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041004.
Paper No: NERS-15-1126
https://doi.org/10.1115/1.4033280
Published Online: October 12, 2016
View Article titled, Computational Fluid Dynamics Simulation of Direct-Contact Condensation Phenomenon of Vapor Jet in Subcooled Water Tank
Open the PDF for Computational Fluid Dynamics Simulation of Direct-Contact Condensation Phenomenon of Vapor Jet in Subcooled Water Tank in another window
Topics: Computational fluid dynamics, Condensation, Mass transfer, Simulation, Subcooling, Temperature, Vapors, Water, Flow (Dynamics), Pressure
Journal Articles

A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water

David Heinze, Thomas Schulenberg, Lars Behnke
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021002.
Paper No: NERS-14-1012
https://doi.org/10.1115/1.4029417
Published Online: March 24, 2015
View Article titled, A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water
Open the PDF for A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water in another window
Topics: Condensation, Drops, Flow (Dynamics), Fluids, Jets, Steam, Water, Turbulence, Subcooling, Temperature
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
Open the PDF for Enhancing Numerical Stability of a Two-Fluid Model by the Use of Interfacial Pressure Terms in another window
Topics: Boiling, Flow (Dynamics), Fluids, Numerical stability, Pressure, Subcooling, Two-phase flow, Simulation, Bubbles