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Proceedings Papers

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Run Luo, Pengfei Wang, Xinyu Wei, Shripad T. Revankar, Fuyu Zhao
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81276
https://doi.org/10.1115/ICONE26-81276
View Paper titled, Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems
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Topics: Thermal hydraulics, Steady state, Transients (Dynamics), Computer simulation, Dynamic models, Engineering simulation, Fuels, Neutron sources, Neutrons, Simulation
Proceedings Papers

Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem

Fei Chao, Jianqiang Shan, Junli Gou, Pan Wu, Li Ge
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81942
https://doi.org/10.1115/ICONE26-81942
View Paper titled, Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem
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Topics: Fluids, Pressure, Water, Gravity (Force), Diffusion (Physics), Flow (Dynamics), Waves, Algorithms, Drag (Fluid dynamics), Pressure gradient
Proceedings Papers

A Space-Time Parallel Method to Solve Space-Dependent Neutron Kinetics Equations in Hexagonal-Z Geometry

Zhizhu Zhang, Yun Cai, Xingjie Peng, Qing Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81213
https://doi.org/10.1115/ICONE26-81213
View Paper titled, A Space-Time Parallel Method to Solve Space-Dependent Neutron Kinetics Equations in Hexagonal-Z Geometry
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Topics: Geometry, Neutrons, Spacetime, Algorithms, Architecture, Nuclear reactor kinetics, Safety, Stability, Thread, Transients (Dynamics)
Proceedings Papers

Application of the Dynamic Rod Worth Measurement Method on WWER

Wenbo Zhao, Zhumin Jiang, Liangzi Wang, Chenlin Wang, Yingrui Yu, Zhaohu Gong, Minxiao Zhong, Tongxian Liu, Hongzhi Xiang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A003, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81055
https://doi.org/10.1115/ICONE26-81055
View Paper titled, Application of the Dynamic Rod Worth Measurement Method on WWER
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Topics: Boron, Dynamics (Mechanics), Geometry, Monte Carlo methods, Neutrons, Nuclear power stations, Pressurized water reactors, Sensors, Shapes, Spacetime
Proceedings Papers

Partially Averaged Navier-Stokes Turbulence Modeling of Flow in 5x5 PWR Fuel Assembly With Spacer Grid

Giacomo Busco, Yassin A. Hassan
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A041, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82366
https://doi.org/10.1115/ICONE26-82366
View Paper titled, Partially Averaged Navier-Stokes Turbulence Modeling of Flow in 5x5 PWR Fuel Assembly With Spacer Grid
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Topics: Flow (Dynamics), Fuels, Manufacturing, Modeling, Pressurized water reactors, Turbulence, Filters, Large eddy simulation, Resolution (Optics), Computer simulation
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66314
https://doi.org/10.1115/ICONE25-66314
View Paper titled, Simulation on Neutron Space-Time Kinetics for Accelerator Driven Sub-Critical System
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Topics: Neutrons, Simulation, Spacetime, Neutron flux, Temperature, Transients (Dynamics), Approximation, Coolants, Fuels, Physics
Proceedings Papers

Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant

B. T. Jiang, J. W. Hines, F. Y. Zhao
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, V002T07A014, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60983
https://doi.org/10.1115/ICONE24-60983
View Paper titled, Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant
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Topics: Accidents, Condition monitoring, Nuclear power stations, Support vector machines, Artificial neural networks, Fuels, Temperature, Transients (Dynamics), Boron, Computers
Proceedings Papers

The Fast Three-Dimensional Space-Time Neutron Kinetic Model for Cartesian Geometry and Cylindrical Geometry

Zhifeng Li, Hongchun Wu, Chenghui Wan, Tianliang Hu
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A063, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60861
https://doi.org/10.1115/ICONE24-60861
View Paper titled, The Fast Three-Dimensional Space-Time Neutron Kinetic Model for Cartesian Geometry and Cylindrical Geometry
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Topics: Geometry, Neutrons, Spacetime, Diffusion (Physics), Algorithms, Computation, Green's function methods, Transients (Dynamics)
Proceedings Papers

Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh

Mingtao He, Hongchun Wu, Liangzhi Cao, Youqi Zheng, ShengCheng Zhou
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, V004T11A014, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31018
https://doi.org/10.1115/ICONE22-31018
View Paper titled, Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh
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Topics: Approximation, Geometry, Neutrons, Spacetime, Transients (Dynamics), Transport processes
Proceedings Papers

Reactor Core Physics Simulation Method for HTR

Chunlin Wei, Zhe Sui, Jun Sun, Wen-zhi Shan
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 721-724, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54369
https://doi.org/10.1115/ICONE20-POWER2012-54369
View Paper titled, Reactor Core Physics Simulation Method for HTR
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Topics: Physics, Simulation, Spacetime, Rods, Cross section (Physics), Cylinders, Design, Fittings, Gas cooled reactors, High temperature
Proceedings Papers

CANDU Reactor Space-Time Kinetic Modeling for Load Following Control

Lingzhi Xia, Jin Jiang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 773-782, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29779
https://doi.org/10.1115/ICONE18-29779
View Paper titled, CANDU Reactor Space-Time Kinetic Modeling for Load Following Control
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Topics: Modeling, Spacetime, Stress, Neutron flux, Control systems, Design, Diffusion (Physics), Eigenfunctions, Matlab, Neutrons
Proceedings Papers

Study of the Space-Time Neutron Multiplication Formula

Jianli Hao, Wenzhen Chen, Shaoming Wang, De Zhang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 49-54, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29279
https://doi.org/10.1115/ICONE18-29279
View Paper titled, Study of the Space-Time Neutron Multiplication Formula
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Topics: Density, Neutrons, Spacetime
Proceedings Papers

Derivation and Analysis of the Criterion for Onset of Density Wave Oscillation in Tubes and Channels With Riser

Yu. Kornienko
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 755-761, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75954
https://doi.org/10.1115/ICONE17-75954
View Paper titled, Derivation and Analysis of the Criterion for Onset of Density Wave Oscillation in Tubes and Channels With Riser
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Topics: Density, Oscillations, Pipeline risers, Risers (Casting), Waves, Flow (Dynamics), Nuclear power stations, Coolants, Enthalpy, Natural convection
Proceedings Papers

Air/Water Counter-Current Flow Experiments in a Model of the Hot Leg of a Pressurised Water Reactor

Christophe Valle´e, Deendarlianto, Matthias Beyer, Dirk Lucas, Helmar Carl
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 807-816, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48374
https://doi.org/10.1115/ICONE16-48374
View Paper titled, Air/Water Counter-Current Flow Experiments in a Model of the Hot Leg of a Pressurised Water Reactor
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Topics: Flow (Dynamics), Water, Computational fluid dynamics, Boilers, Condensers (steam plant), Floods, Geometry, Pressurized water reactors, Reactor vessels, Steam
Proceedings Papers

Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments

Audrius Jasiulevicius, Bal Raj Sehgal
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 705-716, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22081
https://doi.org/10.1115/ICONE10-22081
View Paper titled, Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments
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Topics: Neutrons, Errors, Cross section (Physics), Fuels, Neutron flux, Dynamics (Mechanics), Graphite, Instrumentation, Nuclear power, Nuclear power stations
Proceedings Papers

Transient Analyses for a Molten Salt Transmutation Reactor Using the Extended SIMMER-III Code

Shisheng Wang, Andrei Rineiski, Werner Maschek, Victor Ignatiev
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 91-99, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89209
https://doi.org/10.1115/ICONE14-89209
View Paper titled, Transient Analyses for a Molten Salt Transmutation Reactor Using the Extended SIMMER-III Code
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Topics: Accidents, Equations of state, Fast neutron reactors, Flow (Dynamics), Fuels, Modeling, Molten salt reactors, Neutrons, Spacetime, Transient analysis