1-20 of 41
Uncertainty
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

Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

Available to Purchase
Andy Rivas, Gregory K. Delipei, Jason Hou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021801.
Paper No: NERS-24-1017
https://doi.org/10.1115/1.4066777
Published Online: December 5, 2024
View Articletitled, Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
Open the PDF for Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin in another window
Topics: Electricity (Physics), Optimization, Probability, Maintenance, Steam, Safety, Temperature, Pumps, Uncertainty, Turbines
Journal Articles

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Available to Purchase
Armando Nava-Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021402.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: November 4, 2024
View Articletitled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
Open the PDF for Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications in another window
Topics: Flow (Dynamics), Fluids, Fuels, Heat transfer, Manufacturing, Pressure, Supercritical water reactors, Wall temperature, Water, Wire
Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation

Available to Purchase
Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021101.
Paper No: NERS-24-1037
https://doi.org/10.1115/1.4066344
Published Online: October 22, 2024
View Articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation
Open the PDF for An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation in another window
Topics: Energy budget (Physics), Errors, Flow (Dynamics), Instrumentation, Temperature measurement, Measurement uncertainty, Uncertainty, Sensors, Temperature, Nuclear power stations
Journal Articles

Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results

Available to Purchase
Jared Kirsch, Nima Fathi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041701.
Paper No: NERS-23-1014
https://doi.org/10.1115/1.4065173
Published Online: May 10, 2024
View Articletitled, Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results
Open the PDF for Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results in another window
Topics: Fire, Flames, Flow (Dynamics), Heat flux, Liquid pool fires, Methanol, Simulation, Temperature, Turbulence, Combustion
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

Available to Purchase
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

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Available to Purchase
Thanh Mai Vu, Le Quang Linh Tran, Thi Hong Bui, Nhu Viet Ha Pham
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031501.
Paper No: NERS-23-1039
https://doi.org/10.1115/1.4064780
Published Online: April 17, 2024
View Articletitled, Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries
Open the PDF for Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries in another window
Topics: Eigenvalues, Fast neutron reactors, Neutrons, Nuclear fission, Nuclear reactors, Uncertainty, Uncertainty analysis, Cross section (Physics), Electromagnetic scattering, Radiation scattering
Journal Articles

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Available to Purchase
Lorenzo Loi, Stefano Lorenzi, Antonio Cammi, Carolina Introini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014502.
Paper No: NERS-23-1029
https://doi.org/10.1115/1.4064308
Published Online: December 22, 2023
View Articletitled, A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
Open the PDF for A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset in another window
Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Nuclides, Simulation, Temperature, Uncertainty, Geometry, Errors
Journal Articles

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Available to Purchase
Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Articletitled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
Open the PDF for Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code in another window
Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique

Open Access
Satya Prakash Saraswat, Nicola Forgione, Massimo Emilio Angiolini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021302.
Paper No: NERS-23-1045
https://doi.org/10.1115/1.4063572
Published Online: October 20, 2023
View Articletitled, Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique
Open the PDF for Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique in another window
Topics: Calibration, Differential scanning calorimetry, Heating, Latent heat, Melting, Melting point, Specific heat, Temperature, Thermal properties, Uncertainty
Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

Available to Purchase
Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041802.
Paper No: NERS-23-1050
https://doi.org/10.1115/1.4062865
Published Online: September 15, 2023
View Articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation
Open the PDF for An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation in another window
Topics: Errors, Flow (Dynamics), Instrumentation, Measurement uncertainty, Uncertainty, Nuclear power stations, Sensors, Pipes
Journal Articles

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center

Available to Purchase
Tomáš Czakoj, Michal Košťál, Martin Schulc, Vojtěch Rypar, Evžen Novák, Evžen Losa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032001.
Paper No: NERS-22-1038
https://doi.org/10.1115/1.4056508
Published Online: February 8, 2023
View Articletitled, Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center
Open the PDF for Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center in another window
Topics: Copper, Leakage, Neutrons, Uncertainty, Spectra (Spectroscopy), Neutron sources
Journal Articles

On Cyclotron-Based Production of Gallium-68 Isotope: A Computational Benchmark for the Production Yield & Shielding Considerations

Available to Purchase
Luis Fernando Salas-Tapia, Tian Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 022001.
Paper No: NERS-21-1126
https://doi.org/10.1115/1.4055257
Published Online: September 13, 2022
View Articletitled, On Cyclotron-Based Production of Gallium-68 Isotope: A Computational Benchmark for the Production Yield & Shielding Considerations
Open the PDF for On Cyclotron-Based Production of Gallium-68 Isotope: A Computational Benchmark for the Production Yield & Shielding Considerations in another window
Topics: Cyclotrons, Gallium, Irradiation (Radiation exposure), Isotopes, Particulate matter, Protons, Uncertainty
Journal Articles

Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes

Available to Purchase
Thanh Mai Vu, Donny Hartanto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011502.
Paper No: NERS-21-1143
https://doi.org/10.1115/1.4054080
Published Online: June 7, 2022
View Articletitled, Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes
Open the PDF for Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes in another window
Topics: Cermets, Uncertainty, Ceramics
Journal Articles

Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration

Available to Purchase
Mostafa Y. A. Mostafa, M. Vasyanovich, M. Zhukovsky
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032002.
Paper No: NERS-20-1146
https://doi.org/10.1115/1.4048633
Published Online: May 27, 2022
View Articletitled, Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration
Open the PDF for Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration in another window
Topics: Equilibrium (Physics), Uncertainty, Calibration, Absorption, Filters, Radiation measurement, Sensors
Journal Articles

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

Available to Purchase
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

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

Available to Purchase
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 Articletitled, Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor
Open the PDF for Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor in another window
Topics: Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Neutron activation analysis, Uncertainty
Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Available to Purchase
Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.
Paper No: NERS-21-1029
https://doi.org/10.1115/1.4051447
Published Online: March 16, 2022
View Articletitled, Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
Open the PDF for Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One in another window
Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
Journal Articles

Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation

Available to Purchase
Branislav Vrban, Štefan Čerba, Jakub Lüley, Filip Osuský, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041502.
Paper No: NERS-21-1010
https://doi.org/10.1115/1.4051613
Published Online: March 16, 2022
View Articletitled, Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation
Open the PDF for Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation in another window
Topics: Fuels, Nuclear fission, Uncertainty, Water, Nuclides, Neutrons
Journal Articles

The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term

Available to Purchase
Riku Tuominen, Ville Valtavirta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.
Paper No: NERS-21-1019
https://doi.org/10.1115/1.4051445
Published Online: March 15, 2022
View Articletitled, The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
Open the PDF for The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term in another window
Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
Journal Articles

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Available to Purchase
Andy Jansky, Magnus Langenstein
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 022101.
Paper No: NERS-20-1199
https://doi.org/10.1115/1.4051619
Published Online: October 19, 2021
View Articletitled, Nuclear Regulatory Acceptance of Certified Process Data Reconciliation
Open the PDF for Nuclear Regulatory Acceptance of Certified Process Data Reconciliation in another window
Topics: Measurement uncertainty, Nuclear power stations, Uncertainty, Safety, Feedwater, Flow (Dynamics)