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Proceedings Papers

Experimental Validation of CFD Models Capturing the Thermal-Hydraulics in Liquid Metal Cooled Reactor Plena

Brendan Ward, Thomas Hopkins, Hitesh Bindra
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A037, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16661
https://doi.org/10.1115/ICONE2020-16661
View Paper titled, Experimental Validation of CFD Models Capturing the Thermal-Hydraulics in Liquid Metal Cooled Reactor Plena
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Topics: Computational fluid dynamics, Liquid metals, Thermal hydraulics, Computer simulation, Fluids, Gates (Closures), Safety, Simulation, Acoustics, Backscattering
Proceedings Papers

Stochastic Simulation Method for Reasoning of Dynamic Uncertain Causality Graph (DUCG)

Hao Nie, Qin Zhang
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A023, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16327
https://doi.org/10.1115/ICONE2020-16327
View Paper titled, Stochastic Simulation Method for Reasoning of Dynamic Uncertain Causality Graph (DUCG)
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Topics: Simulation, Algorithms, Probability, Explosions, Fault diagnosis, Nuclear power stations, Statistical distributions
Proceedings Papers

CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package

Roxana-Mihaela Nistor-Vlad, Daniel Dupleac, Ilie Prisecaru, Chris Allison, M. Perez-Ferragut, Judith Hohorst
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A076, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82241
https://doi.org/10.1115/ICONE26-82241
View Paper titled, CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package
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Topics: Accidents, Uncertainty, Uncertainty analysis, Light water reactors, Nuclear reactors, Heat, Nuclear power stations, Safety, Simulation, Statistical distributions
Proceedings Papers

Sensitivity Analysis of Turbulence Models for the Core Inlet Flow Distribution of PWR

Lu-lu Hao, Hong Chen, Su chen Qiu
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A047, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82454
https://doi.org/10.1115/ICONE26-82454
View Paper titled, Sensitivity Analysis of Turbulence Models for the Core Inlet Flow Distribution of PWR
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Topics: Flow (Dynamics), Pressurized water reactors, Sensitivity analysis, Turbulence, Simulation, Computation, Computational fluid dynamics, Geometry, Mesh generation, Computer software
Proceedings Papers

A Monte Carlo Method for Simulating Stochastic Neutron Fields in Criticality Transients

Qi Xu, Zhe Wang, Gang Xiao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A028, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81595
https://doi.org/10.1115/ICONE26-81595
View Paper titled, A Monte Carlo Method for Simulating Stochastic Neutron Fields in Criticality Transients
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Topics: Monte Carlo methods, Neutrons, Transients (Dynamics), Probability, Simulation, Statistical distributions, Accidents, Neutron sources, Nuclear fission
Proceedings Papers

Propagation of Nuclear Data Uncertainties in PWR Pin-Cell Burnup Calculations via Stochastic Sampling

Luigi Mercatali, Yousef Alzaben, Victor Hugo Sanchez Espinoza
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A033, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81711
https://doi.org/10.1115/ICONE26-81711
View Paper titled, Propagation of Nuclear Data Uncertainties in PWR Pin-Cell Burnup Calculations via Stochastic Sampling
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Topics: Pressurized water reactors, Uncertainty, Safety, Design, Economics , Light water reactors, Manufacturing, Modeling, Nuclear reactor safety, Nuclear research
Proceedings Papers

Experimental Study of the Sub-Channel Flow Regimes in 5×5 Rod Bundles With Simplified Grid Spacer

Quanyao Ren, Wenxiong Zhou, Liangming Pan, Hang Liu, Bin Yu, Tingpu Ye, Songsong Li
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A021, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66819
https://doi.org/10.1115/ICONE25-66819
View Paper titled, Experimental Study of the Sub-Channel Flow Regimes in 5×5 Rod Bundles With Simplified Grid Spacer
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Topics: Flow (Dynamics), Fuel rods, Bubbly flow, Turbulence, Two-phase flow, Corners (Structural elements), Pipes, Slug flows, Statistical distributions, Visualization
Proceedings Papers

Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety

Deng Cheng-Cheng, Liu Wei-Li, Yang Jun, Wu Qiao
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A015, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66655
https://doi.org/10.1115/ICONE25-66655
View Paper titled, Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety
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Topics: Safety, Uncertainty, Emergency core cooling systems, Stability, Accidents, Flow (Dynamics), Nuclear power stations, Response surface methodology, Uncertainty analysis, Uncertainty quantification
Proceedings Papers

Sensitivity Study on Forest Fire Breakout and Propagation Conditions for Forest Fire Hazard Curve Evaluations

Yasushi Okano, Hidemasa Yamano
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60047
https://doi.org/10.1115/ICONE24-60047
View Paper titled, Sensitivity Study on Forest Fire Breakout and Propagation Conditions for Forest Fire Hazard Curve Evaluations
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Topics: Fire, Hazards, Nuclear power stations, Probability, Statistical distributions, Heat, Probabilistic risk assessment, Sodium fast reactors, Databases, Meteorology
Proceedings Papers

The Assessment of Containment Functional Failure Frequency in the Revised Level 2 PRA Standard in Japan

Ryoichi Hamazaki, Kazunori Hashimoto, Takayoshi Kusunoki, Chikahiro Satou
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A020, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61019
https://doi.org/10.1115/ICONE24-61019
View Paper titled, The Assessment of Containment Functional Failure Frequency in the Revised Level 2 PRA Standard in Japan
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Topics: Containment, Failure, Accidents, Probability, Explosions, Stress, Damage, Failure mechanisms, Hazards, Steam
Proceedings Papers

Mathematical Modeling for Contingency Determination for Nuclear Power Plant Construction Projects

Wei Zhao, Shenjun Xu
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T12A009, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31254
https://doi.org/10.1115/ICONE22-31254
View Paper titled, Mathematical Modeling for Contingency Determination for Nuclear Power Plant Construction Projects
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Topics: Modeling, Nuclear construction, Nuclear power, Nuclear power stations, Risk management, Simulation, China, Coal power, Databases, Design
Proceedings Papers

Analysis of the Damage Domains of SBO Sequences With RCP Passive Thermal Shutdown

C. Queral, L. Mena-Rosell, G. Jimenez, M. Sánchez-Perea, J. Hortal, J. Gómez-Magán
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30449
https://doi.org/10.1115/ICONE22-30449
View Paper titled, Analysis of the Damage Domains of SBO Sequences With RCP Passive Thermal Shutdown
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Topics: Damage, Safety, Fuels, Cladding systems (Building), Density, Engineering simulation, Failure, Fukushima nuclear disaster, Japan, 2011, Melting, Pressurized water reactors
Proceedings Papers

Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates

David Morton, Bruce Letellier, Jeremy Tejada, David Johnson, Zahra Mohaghegh, Ernie Kee, Vera Moiseytseva, Seyed Reihani, Alexander Zolan
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A026, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30917
https://doi.org/10.1115/ICONE22-30917
View Paper titled, Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates
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Topics: Failure, Fibers, Sensitivity analysis, Simulation models, Computer simulation, Probability, Uncertainty, Errors, Physics, Power stations
Proceedings Papers

PSA Conservatism Analysis and Quantification for the LOFW Accident

Tony X. Kong, Chunrui Deng, Ivan Vrbanic, Ivica Basic
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A011, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15299
https://doi.org/10.1115/ICONE21-15299
View Paper titled, PSA Conservatism Analysis and Quantification for the LOFW Accident
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Topics: Accidents, Uncertainty, Sensitivity analysis, Feedwater, Pressurized water reactors, Probabilistic safety assessment, Safety, Statistical distributions
Proceedings Papers

A Procedure for Characterizing the Range of Input Uncertainty Parameters by the Use of the FFTBM

A. Kovtonyuk, A. Petruzzi, F. D’Auria
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 9-19, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54025
https://doi.org/10.1115/ICONE20-POWER2012-54025
View Paper titled, A Procedure for Characterizing the Range of Input Uncertainty Parameters by the Use of the FFTBM
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Topics: Uncertainty, Nuclear power stations, Databases, Errors, Fast Fourier transforms, Simulation, Statistical distributions, Transients (Dynamics), Uncertainty analysis
Proceedings Papers

Statistical Uncertainty Analyses of Void Fraction Predictions Using Two Different Sampling Strategies: Latin Hypercube and Simple Random Sampling

Augusto Hernandez-Solis, Christian Ekberg, Arvid O¨dega˚rd Jensen, Christophe Demaziere, Ulf Bredolt
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 1059-1068, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30096
https://doi.org/10.1115/ICONE18-30096
View Paper titled, Statistical Uncertainty Analyses of Void Fraction Predictions Using Two Different Sampling Strategies: Latin Hypercube and Simple Random Sampling
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Topics: Porosity, Uncertainty analysis, Uncertainty, Boiling water reactors, Steady state, Transients (Dynamics), Computers, Manufacturing, Nuclear reactors, Pumps
Proceedings Papers

Treatment of Epistemic and Aleatory Uncertainties in the Statistical Analysis of the Neutronic Protection System in CANDU Reactors

D. R. Novog, K. Atkinson, M. Levine, O. Nainer, B. Phan
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 211-220, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48127
https://doi.org/10.1115/ICONE16-48127
View Paper titled, Treatment of Epistemic and Aleatory Uncertainties in the Statistical Analysis of the Neutronic Protection System in CANDU Reactors
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Topics: Statistical analysis, Uncertainty, Safety, Accidents, Instrumentation, Fast neutron reactors, Fuels, Neutrons, Nuclear power stations, Physics
Proceedings Papers

Global Flow Regime Identification in a Rod Bundle Geometry

Sidharth Paranjape, Damian Stefanczyk, Yong Liang, Takashi Hibiki, Mamoru Ishii
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 421-429, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48435
https://doi.org/10.1115/ICONE16-48435
View Paper titled, Global Flow Regime Identification in a Rod Bundle Geometry
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Topics: Flow (Dynamics), Fuel rods, Geometry, Artificial neural networks, Boiling water reactors, Porosity, Self-organization, Signals, Statistical distributions, Two-phase flow
Proceedings Papers

Hot Rod Statistical Method for Large Break Loss of Coolant Accident With CATHARE

Magali Keldenich, Anthony Barbier, Marie-Christine Grouhel, Ce´line Pignoly
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 615-622, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48591
https://doi.org/10.1115/ICONE16-48591
View Paper titled, Hot Rod Statistical Method for Large Break Loss of Coolant Accident With CATHARE
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Topics: Accidents, Cladding systems (Building), Computers, Coolants, Design, Emergency core cooling systems, Licensing, Nuclear reactors, Probability, Safety
Proceedings Papers

Flow Regime Identification in Large Diameter Pipe

Pravin Sawant, Joshua Schelegel, Sidharth Paranjape, Basar Ozar, Takashi Hibiki, Mamoru Ishii
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 341-351, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48311
https://doi.org/10.1115/ICONE16-48311
View Paper titled, Flow Regime Identification in Large Diameter Pipe
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Topics: Flow (Dynamics), Pipes, Porosity, Artificial neural networks, Signals, Gates (Closures), Atmospheric pressure, Bubbly flow, Pressure, Pressure drop