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Journal Articles

Spatial Distribution Assay of Active Neutron Counting

Yuqi Zhang, Xiaoming Xu, Yimei Cheng, Lixia He, Xiao Fan, Haocheng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2025, 11(2): 024501.
Paper No: NERS-24-1011
https://doi.org/10.1115/1.4066883
Published Online: November 22, 2024
View Articletitled, Spatial Distribution Assay of Active Neutron Counting
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Topics: Neutrons, Nuclear fission, Simulation, Cavities, Fittings
Journal Articles

Applicability of the Dose Spiking Electron Paramagnetic Resonance Method for the Quantitative Measurements of Low Doses in Alanine Dosimetry

Lekhnath Ghimire, Edward Waller
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012004.
Paper No: NERS-22-1016
https://doi.org/10.1115/1.4055010
Published Online: September 2, 2022
View Articletitled, Applicability of the Dose Spiking Electron Paramagnetic Resonance Method for the Quantitative Measurements of Low Doses in Alanine Dosimetry
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Topics: Accuracy and precision, Anisotropy, Dosimetry, Electron paramagnetic resonance, Electrons, Errors, Microwaves, Signals, Cavities, Spectra (Spectroscopy)
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011308.
Paper No: NERS-21-1042
https://doi.org/10.1115/1.4051448
Published Online: August 3, 2021
View Articletitled, Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher
Open the PDF for Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher in another window
Topics: Ablation (Vaporization technology), Heat transfer, Melting, Sodium fast reactors, Cavities, High temperature, Ice, Design, Temperature, Water
Journal Articles

Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher

Samyak S. Munot, Ganesh V, Parimal P. Kulkarni, Arun K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041206.
Paper No: NERS-18-1115
https://doi.org/10.1115/1.4043106
Published Online: July 19, 2019
View Articletitled, Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher
Open the PDF for Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher in another window
Topics: Ablation (Vaporization technology), Bricks, Cavities, Temperature, Thermocouples, Vessels, Water, Heat, Accidents, Floods
Journal Articles

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203.
Paper No: NERS-18-1079
https://doi.org/10.1115/1.4042852
Published Online: July 19, 2019
View Articletitled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
Open the PDF for Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor in another window
Topics: Heat, Test facilities, Water, Cavities, Earthquakes, Heat sinks, Boiling water reactors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Fracture (Materials)
Journal Articles

Obstructed View Factor Calculations for Multiple Obstructions in Closed Cavities

Fiaz Mahmood, Huasi Hu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011012.
Paper No: NERS-17-1218
https://doi.org/10.1115/1.4041563
Published Online: January 24, 2019
View Articletitled, Obstructed View Factor Calculations for Multiple Obstructions in Closed Cavities
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Topics: Cavities, Geometry, Pellet fusion, Radiation (Physics), Shades and shadows, String, Computer software, FORTRAN
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 Articletitled, 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

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 Articletitled, 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)