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Proceedings Papers

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Merouane Najar, He Wang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91516
https://doi.org/10.1115/ICONE29-91516
View Paper titled, Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW
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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors
Proceedings Papers

Application of Polynomial Chaos Expansion in Uncertainty Quantification of Reactor Thermal-Hydraulic Calculation

Xiaoyu Zhang, Shubiao Dong, Wei Dong
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A028, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90403
https://doi.org/10.1115/ICONE29-90403
View Paper titled, Application of Polynomial Chaos Expansion in Uncertainty Quantification of Reactor Thermal-Hydraulic Calculation
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Topics: Chaos, Polynomials, Uncertainty quantification
Proceedings Papers

Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

Denis Verrier, Barbara Vezzoni, Barbara Calgaro, Olivier Bernard, Alberto Previti, Clément Lafaurie, Artur Hashymov, Pavlin Groudev, Antoaneta Stefanova, Neli Zaharieva, Frédéric Damian, Pietro Mosca, Daniele Tomatis, Ulrich Bieder, Adrien Willien, Nicolas Dos Santos, Luigi Mercatali, Victor Hugo Sanchez-Espinoza, Nicola Forgione, Sandro Paci
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64169
https://doi.org/10.1115/ICONE28-64169
View Paper titled, Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project
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Topics: Physics, Pressurized water reactors, Safety, Computers, Computational fluid dynamics, Maintenance, Modeling, Nuclear industry, Security, Thermal hydraulics
Proceedings Papers

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64154
https://doi.org/10.1115/ICONE28-64154
View Paper titled, Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Uncertainty Quantification of Seismic Response of Reactor Building Considering Different Modeling Methods

Byunghyun Choi, Akemi Nishida, Ken Muramatsu, Tatsuya Itoi, Tsuyoshi Takada
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A032, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16862
https://doi.org/10.1115/ICONE2020-16862
View Paper titled, Uncertainty Quantification of Seismic Response of Reactor Building Considering Different Modeling Methods
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Topics: Modeling, Nuclear power stations, Uncertainty quantification
Proceedings Papers

Development and Assessment of Data-Driven Digital Twins in a Nearly Autonomous Management and Control System for Advanced Reactors

Linyu Lin, Pascal Rouxelin, Paridhi Athe, Nam Dinh, Jeffrey Lane
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A027, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16813
https://doi.org/10.1115/ICONE2020-16813
View Paper titled, Development and Assessment of Data-Driven Digital Twins in a Nearly Autonomous Management and Control System for Advanced Reactors
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Topics: Control systems, Uncertainty, Databases, Flow (Dynamics), Modeling, Acceptance criteria, Accidents, Artificial neural networks, Design, Errors
Proceedings Papers

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

Edward M. Duchnowski, Seokbin Seo, Nicholas R. Brown
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A046, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16812
https://doi.org/10.1115/ICONE2020-16812
View Paper titled, Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation
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Topics: Cladding systems (Building), Spent nuclear fuels, Storage, Transportation systems, Uncertainty quantification, Hydrogen, Diffusion (Physics), Fuels, Temperature profiles, Uncertainty
Proceedings Papers

Optimization Study for Uncertainty Reduction of In-Pile CHF Experiments in TREAT

Seokbin Seo, Nicholas R. Brown, Robert J. Armstrong, Charles P. Folsom, Colby B. Jensen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A053, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16884
https://doi.org/10.1115/ICONE2020-16884
View Paper titled, Optimization Study for Uncertainty Reduction of In-Pile CHF Experiments in TREAT
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Topics: Critical heat flux, Optimization, Sensitivity analysis, Uncertainty, Coolants, Heat transfer, Transients (Dynamics), Accidents, Fuels, Heat flux
Proceedings Papers

Enhancement of Stochastic Sampling Capability in RMC Code

Guanlin Shi, Yishu Qiu, Kan Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A035, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81982
https://doi.org/10.1115/ICONE26-81982
View Paper titled, Enhancement of Stochastic Sampling Capability in RMC Code
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Topics: Algorithms, Nuclear fission, Safety, Sampling methods, Uncertainty, Uncertainty analysis, Uncertainty quantification
Proceedings Papers

Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation

Hany S. Abdel-Khalik, Dongli Huang, Ondrej Chvala, G. Ivan Maldonado
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A052, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82385
https://doi.org/10.1115/ICONE26-82385
View Paper titled, Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation
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Topics: Nuclear reactors, Simulation, Uncertainty, Physics, Algorithms, Boiling water reactors, Cross section (Physics), Degrees of freedom, Modeling, Uncertainty quantification
Proceedings Papers

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Muhammad Altahhan, Noah McFerran, Jonathan Morrell, Maria Avramova
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A031, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81464
https://doi.org/10.1115/ICONE26-81464
View Paper titled, Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding
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Topics: Ceramic matrix composites, Cladding systems (Building), Silicon, Fuels, Pressurized water reactors, Critical heat flux, Design, Manufacturing, Pressure, Boiling
Proceedings Papers

Investigation on Methods for Uncertainty Quantification of Constitutive Models and the Application in BEPU

Qingwen Xiong, Junli Gou, Jianqiang Shan
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A025, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81425
https://doi.org/10.1115/ICONE26-81425
View Paper titled, Investigation on Methods for Uncertainty Quantification of Constitutive Models and the Application in BEPU
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Topics: Constitutive equations, Uncertainty quantification, Uncertainty, Cladding systems (Building), Design, Safety, Temperature
Proceedings Papers

Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building

Byunghyun Choi, Akemi Nishida, Yinsheng Li, Ken Muramatsu, Tsuyoshi Takada
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82034
https://doi.org/10.1115/ICONE26-82034
View Paper titled, Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building
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Topics: Nuclear reactors, Uncertainty quantification, Uncertainty, Modeling, Accidents, Countermeasures, Design, Engineers, Finite element model, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Development of Uncertainty Quantification Capability for NESTLE

Dongli Huang, Hany S. Abdel-Khalik
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A059, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67797
https://doi.org/10.1115/ICONE25-67797
View Paper titled, Development of Uncertainty Quantification Capability for NESTLE
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Topics: Uncertainty quantification, Uncertainty, Computer software, Cross section (Physics), Physics, Simulation, Algorithms, Cycles, Dimensions, Eigenvalues
Proceedings Papers

The Uncertainty Analysis of Natural Circulation in Molten Salt Reactor Coupling Dakota With GenFlow

Yang Zhao, Zhang-peng Guo, Feng-lei Niu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A068, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66975
https://doi.org/10.1115/ICONE25-66975
View Paper titled, The Uncertainty Analysis of Natural Circulation in Molten Salt Reactor Coupling Dakota With GenFlow
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Topics: Molten salt reactors, Uncertainty analysis, Temperature, Design, Fuels, Optimization, Sensitivity analysis, Shorelines, Accidents, Licensing
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

A Fuel Cycle and Core Design Analysis Method for New Cladding Acceptance Criteria Using PHISICS, RAVEN and RELAP5-3D

Andrea Alfonsi, George L. Mesina, Angelo Zoino, Cristian Rabiti
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A085, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61045
https://doi.org/10.1115/ICONE24-61045
View Paper titled, A Fuel Cycle and Core Design Analysis Method for New Cladding Acceptance Criteria Using PHISICS, RAVEN and RELAP5-3D
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Topics: Acceptance criteria, Cladding systems (Building), Design, Nuclear fuel cycle, Accidents, Physics, Pressurized water reactors, Coolants, Fuels, Leakage
Proceedings Papers

Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System

Masaaki Tanaka, Yasuhiro Miyake
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A028, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30683
https://doi.org/10.1115/ICONE22-30683
View Paper titled, Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System
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Topics: Junctions, Piping systems, Computer simulation, Eddies (Fluid dynamics), Pipes, Vortices, Wakes, Cycles, Fatigue, Temperature
Proceedings Papers

Stochastic Higher-Order Generalized Perturbation Theory for Neutron Diffusion and Transport Calculations

Congjian Wang, Hany S. Abdel-Khalik
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A050, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16572
https://doi.org/10.1115/ICONE21-16572
View Paper titled, Stochastic Higher-Order Generalized Perturbation Theory for Neutron Diffusion and Transport Calculations
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Topics: Diffusion (Physics), Neutrons, Perturbation theory, Scientific computing, Uncertainty quantification, Engineering systems and industry applications, Algorithms, Degrees of freedom, Engineering simulation, Errors
Proceedings Papers

Sensitivity Study of the South Texas Project Power Plant Steady-State Simulations Using RELAP5-3D Coupled With Dakota

O. A. Rodriguez, R. Vaghetto, Y. A. Hassan
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 595-602, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55235
https://doi.org/10.1115/ICONE20-POWER2012-55235
View Paper titled, Sensitivity Study of the South Texas Project Power Plant Steady-State Simulations Using RELAP5-3D Coupled With Dakota
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Topics: Power stations, Simulation, Steady state, Coolants, Pressure, Temperature, Uncertainty quantification, Accidents, Boilers, Computer software