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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

Metamorphic Testing on Nuclide Inventory Tool

Meng Li, Shiyu Yan, Xiaohua Yang, Jie Liu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A001, August 4–5, 2020
Paper No: ICONE2020-16403
DOI: https://doi.org/10.1115/ICONE2020-16403
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Topics: Nuclides, Testing, Algorithms, Approximation, Computer software, Nuclear magnetic resonance, Physics, Software development
Proceedings Papers

Computational Fluid Dynamics As a Tool for Deriving Subchannel Model Parameters: The PSBT Case Study

R. Puragliesi, R. Mukin, I. Clifford, H. Ferroukhi, M. Seidl
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A024, July 22–26, 2018
Paper No: ICONE26-81743
DOI: https://doi.org/10.1115/ICONE26-81743
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Topics: Computational fluid dynamics, Pressure, Friction, Flow (Dynamics), Manufacturing, Pressurized water reactors, Resolution (Optics), Approximation, Boundary-value problems, Computer simulation
Proceedings Papers

Numerical Study of the Amplitude and the Convection Speed of Periodic Large-Scale Vortices in a Square Array of Cylinders Subjected to Axial Flow

Laurent De Moerloose, Jeroen De Ridder, Jan Vierendeels, Joris Degroote
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A023, July 22–26, 2018
Paper No: ICONE26-81730
DOI: https://doi.org/10.1115/ICONE26-81730
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Topics: Axial flow, Convection, Cylinders, Vortices, Pressure, Flow instability, Fluctuations (Physics), Approximation, Boundary-value problems, Engineering simulation
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
Paper No: ICONE26-81441
DOI: https://doi.org/10.1115/ICONE26-81441
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Topics: Sampling methods, Uncertainty analysis, Uncertainty, Nuclear design, Computer software, Approximation, Computation, Design, Economics , Modeling
Proceedings Papers

Neutronic Methodological Benchmarks With Simplified Geometries for the Gas Cooled Reactor Group Constant Generating Tools

E. Temesvari, B. Batki, M. Gren
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A009, July 22–26, 2018
Paper No: ICONE26-81427
DOI: https://doi.org/10.1115/ICONE26-81427
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Topics: Approximation, Doppler effect, Gas cooled reactors, Geometry, Leakage, Manufacturing, Modeling, Optical mirrors, Physics, Safety
Proceedings Papers

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

Wanlin Li, Kan Wang, Ganglin Yu, Yaodong Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A005, July 22–26, 2018
Paper No: ICONE26-81140
DOI: https://doi.org/10.1115/ICONE26-81140
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Topics: Approximation, Computational methods, Cross section (Physics), Density, Design, Errors, Geometry, Manufacturing, Modeling, Neutron flux
Proceedings Papers

Development of Three-Dimensional Neutron Kinetics Code Based on High Order Nodal Expansion Method in Hexagonal-Z Geometry

Guo Chao, Liu Yu, He Hangxing, Liu Luguo, Wang Xiaoyu, Xin Sufang, Li Peiyang, Wu Xiaoli, Yuan Hongsheng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A017, July 22–26, 2018
Paper No: ICONE26-81356
DOI: https://doi.org/10.1115/ICONE26-81356
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Topics: Geometry, Neutrons, Feedback, Polynomials, Approximation, Cross section (Physics), Leakage, Runge-Kutta methods
Proceedings Papers

Development and Application of a 2D/1D Fusion Code With Leakage Reconstruction Method

Liang Liang, Zhouyu Liu, Hongchun Wu, Sheng Wang, Qian Zhang, Qiang Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A022, July 22–26, 2018
Paper No: ICONE26-81507
DOI: https://doi.org/10.1115/ICONE26-81507
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Topics: Leakage, Approximation, Diamonds, Manufacturing, Physics, Tin
Proceedings Papers

Fourier-Bessel Series Model for the Stefan Problem With Internal Heat Generation in Cylindrical Coordinates

Lyudmyla Barannyk, John Crepeau, Patrick Paulus, Ali Siahpush
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A002, July 22–26, 2018
Paper No: ICONE26-81009
DOI: https://doi.org/10.1115/ICONE26-81009
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Topics: Heat, Differential equations, Melting, Solidification, Steady state, Approximation, Fuel rods, Temperature gradient, Temperature profiles, Transients (Dynamics)
Proceedings Papers

Isogeometric Analysis of Pipe System in Nuclear Power Plant

Le Shen, Yang Xia
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A015, July 2–6, 2017
Paper No: ICONE25-66147
DOI: https://doi.org/10.1115/ICONE25-66147
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Topics: Nuclear power stations, Pipes, Simulation, Computer-aided design, Displacement, Geometry, Pipeline systems, Approximation, Boundary-value problems, B-splines
Proceedings Papers

Simulation on Neutron Space-Time Kinetics for Accelerator Driven Sub-Critical System

Yingming Song, Qingyu Gao, Ke Wang, Yaping Guo, Lu Zhang, Yongwei Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A010, July 2–6, 2017
Paper No: ICONE25-66314
DOI: https://doi.org/10.1115/ICONE25-66314
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Topics: Neutrons, Simulation, Spacetime, Neutron flux, Temperature, Transients (Dynamics), Approximation, Coolants, Fuels, Physics
Proceedings Papers

The Rigorous SP3 Theory and Study on its Numerical Verification

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A050, July 2–6, 2017
Paper No: ICONE25-67309
DOI: https://doi.org/10.1115/ICONE25-67309
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Topics: Approximation, Boundary-value problems, Leakage, Scalars
Proceedings Papers

Composite Versus Dispersed Accident Tolerant Nuclear Fuels

Jayangani Ranasinghe, Barbara Szpunar, Ericmoore Jossou, Linu Malakkal, Jerzy A. Szpunar
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A056, July 2–6, 2017
Paper No: ICONE25-67478
DOI: https://doi.org/10.1115/ICONE25-67478
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Topics: Accidents, Composite materials, Nuclear fuels, Fuels, Temperature, Temperature gradient, Thermal conductivity, Aluminum, Approximation, Cracking (Materials)
Proceedings Papers

Research on Detailed Depletion Chain Solving Algorithm With the NUIT Code

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A008, July 2–6, 2017
Paper No: ICONE25-66238
DOI: https://doi.org/10.1115/ICONE25-66238
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Topics: Algorithms, Chain, Nuclides, Approximation, Polynomial approximation
Proceedings Papers

The Measuring of Sodium Droplet Size Distribution and its Impact on the Consequence of Sodium Spray Fire

Wang Guozhi, Du Haiou, Wang Rongdong, Shi Wentao, Piao Jun
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A006, July 2–6, 2017
Paper No: ICONE25-66176
DOI: https://doi.org/10.1115/ICONE25-66176
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Topics: Drops, Fire, Sodium, Sprays, Vessels, Pressure, Nozzles, Particle size, Temperature, Approximation
Proceedings Papers

Passive System Reliability Analysis Based on Improved Support Vector Machine

Hao Ding, Qi Cai, Yongfa Zhang, Lizhi Jiang
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A037, July 2–6, 2017
Paper No: ICONE25-67621
DOI: https://doi.org/10.1115/ICONE25-67621
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Topics: Event history analysis, Support vector machines, Failure, Approximation, Artificial neural networks, Failure mechanisms, Nuclear reactors, Polynomials, Probability, Reliability
Proceedings Papers

Accurate Simulation of HTGR Steam Generator for Pressurized Loss of Forced Cooling Accident

Jianan Lu, Jiong Guo, Fu Li
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A012, June 26–30, 2016
Paper No: ICONE24-60333
DOI: https://doi.org/10.1115/ICONE24-60333
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Topics: Accidents, Boilers, Cooling, Simulation, Very high temperature reactors, Circuits, Heat capacity, Algorithms, Approximation, Boundary-value problems
Proceedings Papers

Comparative Study on Neutronics Characteristics of a 1500 MWe Metal Fuel Sodium-Cooled Fast Reactor

Kazuya Ohgama, Gerardo Aliberti, Nicolas E. Stauff, Shigeo Ohki, Taek K. Kim
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A020, June 26–30, 2016
Paper No: ICONE24-60455
DOI: https://doi.org/10.1115/ICONE24-60455
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Topics: Fuels, Metals, Sodium fast reactors, Nuclear power, Approximation, Cycles, Design, Neutrons, Sensitivity analysis, Sodium
Proceedings Papers

Heat and Mass Transfer Analogy of Steam Condensation With Air Over Vertical External Surface

Jiqiang Su, Yuxiang Wu, Shuliang Huang, Huiqiang Xu, Yanmin Zhou
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A040, June 26–30, 2016
Paper No: ICONE24-60581
DOI: https://doi.org/10.1115/ICONE24-60581
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Topics: Condensation, Heat, Mass transfer, Steam, Approximation, Diffusion (Physics), Experimental methods, Gases, Helium, Suction