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Proceedings Papers

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Yuhan Li, Bo Kuang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92431
https://doi.org/10.1115/ICONE29-92431
View Paper titled, A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology
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Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design
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

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

Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method

Hongkuan Liao, Qing Li, Yingrui Yu, Yuying Hu, Lei Wu, Chenlin Wang, Jinyu Wang, Jinghui Wang, Peng Xiao
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81441
https://doi.org/10.1115/ICONE26-81441
View Paper titled, Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method
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Topics: Sampling methods, Uncertainty analysis, Uncertainty, Nuclear design, Computer software, Approximation, Computation, Design, Economics , Modeling
Proceedings Papers

Uncertainty Analysis for the Steady-Stated BEAVRS Benchmark Problem at ARO and ARI Situations

Chenghui Wan, Liangzhi Cao, Hongchun Wu
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A005, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66191
https://doi.org/10.1115/ICONE25-66191
View Paper titled, Uncertainty Analysis for the Steady-Stated BEAVRS Benchmark Problem at ARO and ARI Situations
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Topics: Uncertainty analysis, Uncertainty, Engineering simulation, Physics, Simulation, Fuels, Sampling methods
Proceedings Papers

Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression

Chunzhen Yang, Jingquan Liu, Yuyun Zeng, Muhammad Saeed
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T01A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61114
https://doi.org/10.1115/ICONE24-61114
View Paper titled, Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression
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Topics: Support vector machines, Uncertainty, Modeling, Nuclear power stations, Algorithms, Carbon steel, In-service inspection, Maintenance, Pipes, Sampling methods
Proceedings Papers

Seismic Fragility Study for High-Pressure Emergency Cooling Water Tanks of Loviisa Nuclear Power Plant

Jukka Ka¨hko¨nen, Pentti Varpasuo
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 429-434, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29181
https://doi.org/10.1115/ICONE18-29181
View Paper titled, Seismic Fragility Study for High-Pressure Emergency Cooling Water Tanks of Loviisa Nuclear Power Plant
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Topics: Cooling, Emergencies, High pressure (Physics), Nuclear power stations, Water, Probability, Failure, Nozzles, Pipes, Shapes
Proceedings Papers

Research on Monte Carlo Perturbation Calculation Methods Applied in Reactor Physics

Ze-guang Li, Kan Wang, Gang-lin Yu
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 543-547, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75584
https://doi.org/10.1115/ICONE17-75584
View Paper titled, Research on Monte Carlo Perturbation Calculation Methods Applied in Reactor Physics
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Topics: Computational methods, Design, Multidimensional systems, Physics, Sampling methods, Temperature, Uncertainty analysis
Proceedings Papers

Comparison of Realistic Large Break LOCA Analyses of a 3-Loop Westinghouse Plant Using Response Surface and Statistical Sampling Techniques

K. Muftuoglu, K. Ohkawa, C. Frepoli, M. Nissley
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 811-818, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49499
https://doi.org/10.1115/ICONE12-49499
View Paper titled, Comparison of Realistic Large Break LOCA Analyses of a 3-Loop Westinghouse Plant Using Response Surface and Statistical Sampling Techniques
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Topics: Response surface methodology, Sampling methods, Uncertainty, Emergency core cooling systems, Transients (Dynamics), Accidents, Coolants, Probability, Regression models, Statistics
Proceedings Papers

Development of the Analysis Method for the Radioactivity Concentration Estimation of Soils for a Regulatory Clearance

Dae-Seok Hong, Jong-Sik Shon, Tae-Kuk Kim, Han-Seok Cho
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 481-484, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89443
https://doi.org/10.1115/ICONE14-89443
View Paper titled, Development of the Analysis Method for the Radioactivity Concentration Estimation of Soils for a Regulatory Clearance
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Topics: Clearances (Engineering), Radioactivity, Soil, Concretes, Decontamination, Errors, Nuclear decommissioning, Nuclear power, Nuclides, Particulate matter