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Proceedings Papers

Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials

Deyan Kong, Xu Liu, Jie Cheng, Jianjun Wang, Jinqiang Zhang, Dingyong Chen, Qingzhao Li, Yanting Liu

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A029, August 8–12, 2022

Paper No: ICONE29-91951

DOI: https://doi.org/10.1115/ICONE29-91951

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Topics: Chaos, Failure, Polynomials, Pressurized water reactors, Probability, Stress corrosion cracking, Uncertainty analysis

Proceedings Papers

Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR

Yuxuan Liang, Xiang Wang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A068, August 8–12, 2022

Paper No: ICONE29-92887

DOI: https://doi.org/10.1115/ICONE29-92887

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Topics: Accidents, Fuels, Sensitivity analysis, Uncertainty analysis

Proceedings Papers

Study on the Method for the Safety-Related Instrument Calibration Periodic Test Interval Extension of Nuclear Power Unit With Digital I&C System Based on Setpoint and Uncertainty Analysis

Zhao Zhang, Yong Zhang, Zi-Chun Wang, Bo-Wen Tang, Yong-Hui Zhou, Min-Hua Su, Wen-Bo Luo

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A029, August 8–12, 2022

Paper No: ICONE29-92949

DOI: https://doi.org/10.1115/ICONE29-92949

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Topics: Calibration, Instrumentation, Nuclear power, Safety, Uncertainty analysis

Proceedings Papers

CFD Uncertainty Analysis of Once-Through Steam Generator

Han Feng, Youxin Zhou, Yousen Hu, Naihua Wang, Xixi Zhu

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A004, August 8–12, 2022

Paper No: ICONE29-89095

DOI: https://doi.org/10.1115/ICONE29-89095

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Topics: Boilers, Chaos, Computational fluid dynamics, Polynomials, Uncertainty analysis

Proceedings Papers

Sensitivity and Uncertainty Analysis of Molten Corium-Concrete Interaction (MCCI) for ALWR During Severe Accident

Zijie Wu, Peng Chen, Xinhao Zhao, Chao Guo, Dekui Zhan, Shaoxiong Xia

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A001, August 8–12, 2022

Paper No: ICONE29-89217

DOI: https://doi.org/10.1115/ICONE29-89217

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Topics: Accidents, Concretes, Uncertainty analysis

Proceedings Papers

Study on the Method for the Safety-Related Instrument Calibration Surveillance Interval Extension of Nuclear Power Unit With Analog I&C System Based on Setpoint and Uncertainty Analysis

Yong Zhang, Zhao Zhang, Zi-Chun Wang, Yong-Hui Zhou, Bo-Wen Tang, Min-Hua Su, Wen-Bo Luo

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A052, August 8–12, 2022

Paper No: ICONE29-92941

DOI: https://doi.org/10.1115/ICONE29-92941

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Topics: Calibration, Instrumentation, Nuclear power, Safety, Surveillance, Uncertainty analysis

Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022

Paper No: ICONE29-89017

DOI: https://doi.org/10.1115/ICONE29-89017

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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis

Proceedings Papers

Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

Landon Conner, Clarence L. Worrell, James P. Spring, Jun Liao

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A035, August 4–6, 2021

Paper No: ICONE28-66619

DOI: https://doi.org/10.1115/ICONE28-66619

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Topics: Accidents, Machinery, Metamodeling, Simulation, Artificial neural networks, Machine learning, Manufacturing, Nuclear industry, Optimization, Safety

Proceedings Papers

Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation

Xinlu Tian, Jianping Jing, Shaoxin Zhuang, Haiying Chen

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A002, August 4–6, 2021

Paper No: ICONE28-64393

DOI: https://doi.org/10.1115/ICONE28-64393

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Topics: Safety, Uncertainty analysis

Proceedings Papers

Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR

Mingqiang Song, Ningna Zhang, Xiaoming Yang, Rubing Ma, Zhiyi Yang, Chao Ding

Paper No: ICONE28-64749

DOI: https://doi.org/10.1115/ICONE28-64749

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Topics: Accidents, Sensitivity analysis, Hydrogen production, Nuclear industry, China, Coolants, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pressure

Proceedings Papers

Low Dose Assessment Uncertainty Analysis for Landauer ® nanoDot™ OSLDs

Egemen Aras, Robert Hayes

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A074, August 4–6, 2021

Paper No: ICONE28-65591

DOI: https://doi.org/10.1115/ICONE28-65591

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Topics: Background radiation, Dosimeters, Radiation (Physics), Safety, Security, Statistics, Uncertainty, Uncertainty analysis

Proceedings Papers

Time Series Clustering and Classification for Uncertainty Analysis by MAAP5 Code

Ikuo Kinoshita

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, V001T01A009, August 4–5, 2020

Paper No: ICONE2020-16437

DOI: https://doi.org/10.1115/ICONE2020-16437

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Topics: Time series, Uncertainty analysis, Uncertainty, Hydrogen, Errors, Regression models, Algorithms, Damage, Fuels

Proceedings Papers

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Kenneth C. Wagner, David L. Y. Louie

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A045, August 4–5, 2020

Paper No: ICONE2020-16584

DOI: https://doi.org/10.1115/ICONE2020-16584

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Topics: Accidents, Fire, Explosions, Radioisotopes, Aerosols, Model development, Nuclear power stations, Probabilistic risk assessment, Safety, Spent nuclear fuels

Proceedings Papers

Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors

Tao Liu, Zeyun Wu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A015, August 4–5, 2020

Paper No: ICONE2020-16242

DOI: https://doi.org/10.1115/ICONE2020-16242

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Topics: Accidents, Flow (Dynamics), Uncertainty, Uncertainty analysis

Proceedings Papers

Nuclear Data Sensitivity and Uncertainty Analysis for Generalized Response With RMC Code

Guanlin Shi, Conglong Jia, Shanfang Huang, Kaiwen Li, Lei Zheng

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A003, August 4–5, 2020

Paper No: ICONE2020-16062

DOI: https://doi.org/10.1115/ICONE2020-16062

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Topics: Uncertainty analysis

Proceedings Papers

Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions

Hongbin Zhang, Cole Blakely, Jianguo Yu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A005, August 4–5, 2020

Paper No: ICONE2020-16098

DOI: https://doi.org/10.1115/ICONE2020-16098

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Topics: Fuel rods, Physics, Probability, Accidents, Cycles, Light water reactors, Coolants, Design, Fuels, Pressurized water reactors

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

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

Paper No: ICONE26-82241

DOI: https://doi.org/10.1115/ICONE26-82241

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Topics: Accidents, Uncertainty, Uncertainty analysis, Light water reactors, Nuclear reactors, Heat, Nuclear power stations, Safety, Simulation, Statistical distributions

Proceedings Papers

Prediction of Subcooled Boiling With Uncertainties From Boundary Conditions and Interaction Models

Tenglong Cong, Minjun Peng, Xiang Zhang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A003, July 22–26, 2018

Paper No: ICONE26-81101

DOI: https://doi.org/10.1115/ICONE26-81101

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Topics: Boiling, Boundary-value problems, Subcooling, Uncertainty, Computational fluid dynamics, Calibration, Gaussian distribution, Model validation, Statistical analysis, Uncertainty analysis

Proceedings Papers

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018

Paper No: ICONE26-81694

DOI: https://doi.org/10.1115/ICONE26-81694

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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams

2 3 4

NARROW

Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials

Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR

Study on the Method for the Safety-Related Instrument Calibration Periodic Test Interval Extension of Nuclear Power Unit With Digital I&C System Based on Setpoint and Uncertainty Analysis

CFD Uncertainty Analysis of Once-Through Steam Generator

Sensitivity and Uncertainty Analysis of Molten Corium-Concrete Interaction (MCCI) for ALWR During Severe Accident

Study on the Method for the Safety-Related Instrument Calibration Surveillance Interval Extension of Nuclear Power Unit With Analog I&C System Based on Setpoint and Uncertainty Analysis

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation

Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR

Low Dose Assessment Uncertainty Analysis for Landauer ® nanoDot™ OSLDs

Time Series Clustering and Classification for Uncertainty Analysis by MAAP5 Code

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors

Nuclear Data Sensitivity and Uncertainty Analysis for Generalized Response With RMC Code

Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

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

Prediction of Subcooled Boiling With Uncertainties From Boundary Conditions and Interaction Models

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

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