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Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021

Paper No: ICONE28-64169

DOI: https://doi.org/10.1115/ICONE28-64169

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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

Paper No: ICONE28-64154

DOI: https://doi.org/10.1115/ICONE28-64154

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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 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

Paper No: ICONE2020-16812

DOI: https://doi.org/10.1115/ICONE2020-16812

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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

Paper No: ICONE2020-16884

DOI: https://doi.org/10.1115/ICONE2020-16884

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Topics: Critical heat flux, Optimization, Sensitivity analysis, Uncertainty, Coolants, Heat transfer, Transients (Dynamics), Accidents, Fuels, Heat flux

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

Paper No: ICONE2020-16862

DOI: https://doi.org/10.1115/ICONE2020-16862

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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

Paper No: ICONE2020-16813

DOI: https://doi.org/10.1115/ICONE2020-16813

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Topics: Control systems, Uncertainty, Databases, Flow (Dynamics), Modeling, Acceptance criteria, Accidents, Artificial neural networks, Design, Errors

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

Paper No: ICONE26-81464

DOI: https://doi.org/10.1115/ICONE26-81464

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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

Paper No: ICONE26-81425

DOI: https://doi.org/10.1115/ICONE26-81425

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Topics: Constitutive equations, Uncertainty quantification, Uncertainty, Cladding systems (Building), Design, Safety, Temperature

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

Paper No: ICONE26-81982

DOI: https://doi.org/10.1115/ICONE26-81982

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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

Paper No: ICONE26-82385

DOI: https://doi.org/10.1115/ICONE26-82385

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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

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

Paper No: ICONE26-82034

DOI: https://doi.org/10.1115/ICONE26-82034

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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

Paper No: ICONE25-67797

DOI: https://doi.org/10.1115/ICONE25-67797

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Topics: Uncertainty quantification, Uncertainty, Computer software, Cross section (Physics), Physics, Simulation, Algorithms, Cycles, Dimensions, Eigenvalues

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

Paper No: ICONE25-66655

DOI: https://doi.org/10.1115/ICONE25-66655

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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

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

Paper No: ICONE25-66975

DOI: https://doi.org/10.1115/ICONE25-66975

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Topics: Molten salt reactors, Uncertainty analysis, Temperature, Design, Fuels, Optimization, Sensitivity analysis, Shorelines, Accidents, Licensing

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

Paper No: ICONE24-61045

DOI: https://doi.org/10.1115/ICONE24-61045

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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

Paper No: ICONE22-30683

DOI: https://doi.org/10.1115/ICONE22-30683

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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

Paper No: ICONE21-16572

DOI: https://doi.org/10.1115/ICONE21-16572

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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

Paper No: ICONE20-POWER2012-55235

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55235

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Topics: Power stations, Simulation, Steady state, Coolants, Pressure, Temperature, Uncertainty quantification, Accidents, Boilers, Computer software

NARROW

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

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

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

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

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

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

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

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

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

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

Enhancement of Stochastic Sampling Capability in RMC Code

Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation

Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building

Development of Uncertainty Quantification Capability for NESTLE

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

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

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

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

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

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

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