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Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA

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Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: April 22, 2024
View Articletitled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
Open the PDF for Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA in another window
Topics: Boiling water reactors, Hydrogen, Oxidation, Simulation, Uncertainty analysis, Zirconium, Accidents, Sensitivity analysis, Temperature, Uncertainty
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

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Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
Paper No: NERS-22-1165
https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Articletitled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
Open the PDF for ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code in another window
Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

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Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
Paper No: NERS-21-1160
https://doi.org/10.1115/1.4055328
Published Online: December 14, 2022
View Articletitled, Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
Open the PDF for Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors in another window
Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants
Journal Articles

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

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Emmanuel K. Boafo, Emmanuel Numapau Gyamfi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.
Paper No: NERS-21-1094
https://doi.org/10.1115/1.4053050
Published Online: May 26, 2022
View Articletitled, Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA
Open the PDF for Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA in another window
Topics: Accidents, Hydrogen, Sensitivity analysis, Uncertainty, Uncertainty quantification, Uncertainty analysis, Design, Optimization
Journal Articles

Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model

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Dinara Ermakova, Haruko Wainwright, LianGe Zheng, Ian Shirley, Hannah Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041902.
Paper No: NERS-20-1174
https://doi.org/10.1115/1.4050297
Published Online: May 13, 2021
View Articletitled, Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model
Open the PDF for Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model in another window
Topics: Polishing equipment, Rocks, Sensitivity analysis, Simulation, Chemical processes, Minerals, Density
Journal Articles

The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

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ZhiGang Li, Wei Liu, PingZhou Ming, Ping An, Wei Lu, JunJie Pan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041103.
Paper No: NERS-19-1153
https://doi.org/10.1115/1.4047093
Published Online: September 4, 2020
View Articletitled, The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition
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Topics: Sensitivity analysis
Journal Articles

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

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María Freiría López, Michael Buck, Jörg Starflinger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041110.
Paper No: NERS-19-1166
https://doi.org/10.1115/1.4047094
Published Online: September 4, 2020
View Articletitled, Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products
Open the PDF for Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products in another window
Topics: Concretes, Water, Fukushima nuclear disaster, Japan, 2011, Vessels, Sensitivity analysis
Journal Articles

Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code

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Rosario Delgado-Tardáguila, Marisol Corisco, Antonio Espejo, Daniel Navarro, Javier Riverola
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020909.
Paper No: NERS-18-1057
https://doi.org/10.1115/1.4042358
Published Online: March 15, 2019
View Articletitled, Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code
Open the PDF for Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code in another window
Topics: Design, Fuels, Nucleate boiling, Thermal diffusion, Turbulence, Enthalpy, Momentum, Heat flux, Flow (Dynamics), Sensitivity analysis
Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

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Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.
Paper No: NERS-17-1163
https://doi.org/10.1115/1.4040887
Published Online: September 10, 2018
View Articletitled, Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
Open the PDF for Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant in another window
Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations
Journal Articles

Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

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Bruno Gonfiotti, Sandro Paci
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020902.
Paper No: NERS-16-1115
https://doi.org/10.1115/1.4038059
Published Online: March 5, 2018
View Articletitled, Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes
Open the PDF for Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes in another window
Topics: Aerosols, Containment, Nuclear fission, Temperature, Sensitivity analysis, Water, Condensers (steam plant), Thermal hydraulics, Condensation
Journal Articles

Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries

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Attila Kiss, Andrey Churkin, Darwan S. Pilkhwal, Abhijeet M. Vaidya, Walter Ambrosini, Andrea Pucciarelli, Krishna Podila, Yanfei Rao, Laurence Leung, Chen Yuzhou, Mark Anderson, Meng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011001.
Paper No: NERS-17-1047
https://doi.org/10.1115/1.4038162
Published Online: December 4, 2017
View Articletitled, Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries
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Topics: Computational fluid dynamics, Sensitivity analysis, Wall temperature, Heat transfer, Turbulence, Boundary-value problems
Journal Articles

Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants

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A. Gad-Briggs, P. Pilidis
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011017.
Paper No: NERS-15-1213
https://doi.org/10.1115/1.4033398
Published Online: December 20, 2016
View Articletitled, Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
Open the PDF for Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants in another window
Topics: Compressors, Cycles, Helium, Pressure, Sensitivity analysis, Temperature, Turbines, Thermal efficiency, Gas turbines
Journal Articles

Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis

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Jia Yang, Rongyong Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014501.
Paper No: NERS-15-1137
https://doi.org/10.1115/1.4035285
Published Online: December 20, 2016
View Articletitled, Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis
Open the PDF for Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis in another window
Topics: Condensers (steam plant), Cooling, Optimization, Sensitivity analysis, Steam turbines, Design, Nuclear power stations, Tariffs, Cooling towers, Pipes