1-20 of 66
Uncertainty analysis
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
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
Open the PDF for Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients in another window
Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92887
https://doi.org/10.1115/ICONE29-92887
View Paper titled, Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR
Open the PDF for Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92949
https://doi.org/10.1115/ICONE29-92949
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Calibration, Instrumentation, Nuclear power, Safety, 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92941
https://doi.org/10.1115/ICONE29-92941
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Calibration, Instrumentation, Nuclear power, Safety, Surveillance, 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89095
https://doi.org/10.1115/ICONE29-89095
View Paper titled, CFD Uncertainty Analysis of Once-Through Steam Generator
Open the PDF for CFD Uncertainty Analysis of Once-Through Steam Generator in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89217
https://doi.org/10.1115/ICONE29-89217
View Paper titled, Sensitivity and Uncertainty Analysis of Molten Corium-Concrete Interaction (MCCI) for ALWR During Severe Accident
Open the PDF for Sensitivity and Uncertainty Analysis of Molten Corium-Concrete Interaction (MCCI) for ALWR During Severe Accident in another window
Topics: Accidents, Concretes, Uncertainty analysis
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91951
https://doi.org/10.1115/ICONE29-91951
View Paper titled, Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials
Open the PDF for Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials in another window
Topics: Chaos, Failure, Polynomials, Pressurized water reactors, Probability, Stress corrosion cracking, Uncertainty 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66619
https://doi.org/10.1115/ICONE28-66619
View Paper titled, Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code
Open the PDF for Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64393
https://doi.org/10.1115/ICONE28-64393
View Paper titled, Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation
Open the PDF for Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation in another window
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
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, V003T09A006, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64749
https://doi.org/10.1115/ICONE28-64749
View Paper titled, Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR
Open the PDF for Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65591
https://doi.org/10.1115/ICONE28-65591
View Paper titled, Low Dose Assessment Uncertainty Analysis for Landauer ® nanoDot™ OSLDs
Open the PDF for Low Dose Assessment Uncertainty Analysis for Landauer ® nanoDot™ OSLDs in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16437
https://doi.org/10.1115/ICONE2020-16437
View Paper titled, Time Series Clustering and Classification for Uncertainty Analysis by MAAP5 Code
Open the PDF for Time Series Clustering and Classification for Uncertainty Analysis by MAAP5 Code in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16584
https://doi.org/10.1115/ICONE2020-16584
View Paper titled, MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant
Open the PDF for MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16242
https://doi.org/10.1115/ICONE2020-16242
View Paper titled, Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors
Open the PDF for Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16062
https://doi.org/10.1115/ICONE2020-16062
View Paper titled, Nuclear Data Sensitivity and Uncertainty Analysis for Generalized Response With RMC Code
Open the PDF for Nuclear Data Sensitivity and Uncertainty Analysis for Generalized Response With RMC Code in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16098
https://doi.org/10.1115/ICONE2020-16098
View Paper titled, Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions
Open the PDF for Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions in another window
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
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
Open the PDF for Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding in another window
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
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
Open the PDF for CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package in another window
Topics: Accidents, Uncertainty, Uncertainty analysis, Light water reactors, Nuclear reactors, Heat, Nuclear power stations, Safety, Simulation, Statistical distributions
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
Open the PDF for Enhancement of Stochastic Sampling Capability in RMC Code in another window
Topics: Algorithms, Nuclear fission, Safety, Sampling methods, Uncertainty, Uncertainty analysis, Uncertainty quantification
Proceedings Papers

Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE

Jinlin Niu, Lidong Wang, Jiong Guo, Fu Li
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A033, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82155
https://doi.org/10.1115/ICONE26-82155
View Paper titled, Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE
Open the PDF for Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE in another window
Topics: Carbon reinforced plastics, Temperature, Convection, Coolants, Electrical conductivity, Fuels, Helium, Modeling, Power density, Shells