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Journal Articles

Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

Radojko Jaćimović, Maria Ângela de Barros Correia Menezes
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041504.
Paper No: NERS-21-1007
https://doi.org/10.1115/1.4051249
Published Online: March 22, 2022
View Article titled, Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor
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Topics: Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Neutron activation analysis, Uncertainty
Journal Articles

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection

Claude Jamond, Elena Martin Lopez, Xue-Nong Chen, Nathalie Girault, Pierre Gubernatis, Andrei Rineiski
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011325.
Paper No: NERS-20-1142
https://doi.org/10.1115/1.4052489
Published Online: December 14, 2021
View Article titled, Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection
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Topics: Fuels, Heat transfer, Modeling, Natural convection, Heat, Temperature, Flux (Metallurgy)
Journal Articles

Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes

Xianliang Lei, Huixiong Li, Weiqiang Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031017.
Paper No: NERS-15-1105
https://doi.org/10.1115/1.4032872
Published Online: June 17, 2016
View Article titled, Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes
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Topics: Flux (Metallurgy), Heat, Heat transfer, Numerical analysis, Pressure, Supercritical fluids, Temperature, Turbulence, Wall temperature, Heat flux
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

Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031004.
Paper No: NERS-14-1027
https://doi.org/10.1115/1.4029521
Published Online: May 20, 2015
View Article titled, Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
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Topics: Cross section (Physics), Density, Flux (Metallurgy), Fuels, Nuclides, Spectra (Spectroscopy), Nuclear fission, Fast neutron reactors
Journal Articles

Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor

Michal Košťál, Vlastimil Juříček, Ján Milčák, Vojtěch Rypar, Antonín Kolros
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2015, 1(2): 024509.
Paper No: NERS-14-1019
https://doi.org/10.1115/1.4029284
Published Online: March 24, 2015
View Article titled, Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor
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Topics: Neutrons, Flux (Metallurgy), Neutron flux