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Proceedings Papers

Retracted: “Power Control System Design for Heat Pipe Cooled Reactor Based on Model Predictive Control” [2022 29th International Conference on Nuclear Engineering, Volume 15] Shenzhen, China and Virtual, Online, August 8–12, 2022, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8650-2, Copyright © 2022 by ASME. Paper No. ICONE29-89495, V015T16A014; 8 pages; doi: https://doi.org/10.1115/ICONE29-89495

ASME
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89495
https://doi.org/10.1115/ICONE29-89495
View Paper titled, Retracted: “Power Control System Design for Heat Pipe Cooled Reactor Based on Model Predictive Control” [2022 29th International Conference on Nuclear Engineering, Volume 15] Shenzhen, China and Virtual, Online, August 8–12, 2022, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8650-2, Copyright © 2022 by ASME. Paper No. ICONE29-89495, V015T16A014; 8 pages; doi: https://doi.org/10.1115/ICONE29-89495
Open the PDF for Retracted: “Power Control System Design for Heat Pipe Cooled Reactor Based on Model Predictive Control” [2022 29th International Conference on Nuclear Engineering, Volume 15] Shenzhen, China and Virtual, Online, August 8–12, 2022, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8650-2, Copyright © 2022 by ASME. Paper No. ICONE29-89495, V015T16A014; 8 pages; doi: https://doi.org/10.1115/ICONE29-89495 in another window
Topics: China, Control systems, Design, Heat pipes, Nuclear engineering, Pipes, Predictive control, Pressure vessels
Proceedings Papers

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Yuchao Wang, Daogang Lu, Fei Zhao, Yu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A071, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92039
https://doi.org/10.1115/ICONE29-92039
View Paper titled, Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants
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Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels
Proceedings Papers

TCR Central Shutdown Rod Fine Motion Control

Venugopal K. Varma, Eliott Fountain, Earle Burkhardt, Sacit Cetiner, Dustin Ottinger
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90217
https://doi.org/10.1115/ICONE29-90217
View Paper titled, TCR Central Shutdown Rod Fine Motion Control
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Topics: Electromagnets, Motion control, Design, Pressure vessels, Actuators, Artificial intelligence, Engineering prototypes, Engines, Gravity (Force), Helium
Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Yaoxin Ye, Jun Zhao, Pengfei Bao
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93545
https://doi.org/10.1115/ICONE29-93545
View Paper titled, Verification and Validation of JMCT Monte Carlo Code in CPR1000
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Topics: China, Computer technology, Design, Fluence (Radiation measurement), Irradiation (Radiation exposure), Monte Carlo methods, Neutrons, Nuclear engineering, Nuclear power stations, Particulate matter
Proceedings Papers

Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions

Guanhui Xie, Runcheng Li, Tianyi Wei, Zhikang Lin, Dongyang Li, Sichao Tan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89228
https://doi.org/10.1115/ICONE29-89228
View Paper titled, Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions
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Topics: Accidents, Boron, Flow (Dynamics), Fluids, Reactor vessels, Water, Pressure vessels, Coolants, Safety, Fluid dynamics
Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Songyang Liu, Xiang Wang
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, V001T04A014, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65689
https://doi.org/10.1115/ICONE28-65689
View Paper titled, Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor
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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China
Proceedings Papers

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Mingpeng Chen, Guanhui Xie, Dongyang Li, Sichao Tan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A038, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65770
https://doi.org/10.1115/ICONE28-65770
View Paper titled, Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method
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Topics: Boron, Flow measurement, Fluids, Lasers, Reactor vessels, Slug flows, Coolants, Flow (Dynamics), Pressure vessels, Annulus
Proceedings Papers

Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing (HIP) Process

John Sulley, Phil Wallace, Ted Warner, Gary Jones
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, V001T06A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16035
https://doi.org/10.1115/ICONE2020-16035
View Paper titled, Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing (HIP) Process
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Topics: Hot pressing, Reactor vessels, Vessels, Nuclear power stations, Pressure vessels, Welding, Alloy steel, Electron beam welding, Energy generation, Fillers (Materials)
Proceedings Papers

Fatigue Risk Evaluation of a Pressure Vessel Plug Subject to Flow Induced Vibration

Robert Wang, Louis Chang, Tom Hurst, Antony Hurst
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, V001T06A017, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16650
https://doi.org/10.1115/ICONE2020-16650
View Paper titled, Fatigue Risk Evaluation of a Pressure Vessel Plug Subject to Flow Induced Vibration
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Topics: Fatigue, Flow-induced vibrations, Fluids, Pressure vessels, Random vibration, Risk assessment
Proceedings Papers

Residual Stress Measurement of Sealing Glass Based on Optical Fiber Sensing Technology

Li Mingze, Fan Zhichun, Diao Xingzhong, Yan He
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82135
https://doi.org/10.1115/ICONE26-82135
View Paper titled, Residual Stress Measurement of Sealing Glass Based on Optical Fiber Sensing Technology
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Topics: Glass, Optical fiber, Sealing (Process), Stress, Metals, Fiber Bragg gratings, Containment, Diffraction gratings, Fiber optic sensors, Finite element model
Proceedings Papers

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

Jian Li, Ding She, Lei Shi, Jing Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A046, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82242
https://doi.org/10.1115/ICONE26-82242
View Paper titled, Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT
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Topics: Fuels, Particulate matter, Failure, Very high temperature reactors, Accidents, Equipment performance, Gas cooled reactors, High temperature, Pressure vessels, Probability
Proceedings Papers

Experimental Investigation and Model Analysis on Upper Plenum Entrainment in AP1000

Y. Xiang, Y. W. Wu, Mingjun Wang, W. X. Tian, S. Z. Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A049, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82303
https://doi.org/10.1115/ICONE26-82303
View Paper titled, Experimental Investigation and Model Analysis on Upper Plenum Entrainment in AP1000
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Topics: Coolants, Dimensionless numbers, Drops, Energy conservation, Errors, Melting, Pressure vessels
Proceedings Papers

Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles

K. H. Deng, Y. Zhang, C. L. Wang, Y. P. Zhang, W. X. Tian, S. Z. Qiu, G. H. Su, Y. Wang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81844
https://doi.org/10.1115/ICONE26-81844
View Paper titled, Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles
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Topics: Critical heat flux, Flat plates, Pressure vessels, Heat, Accidents, Cooling, Heating, Leakage, Nuclear reactors, Pool boiling
Proceedings Papers

VVER 1000 Pressurizer System and Control Modelling in Dymola

Anna Fořtová, Filip Ježek
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81263
https://doi.org/10.1115/ICONE26-81263
View Paper titled, VVER 1000 Pressurizer System and Control Modelling in Dymola
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Topics: Actuators, Automatic control, Boilers, Circuits, Computer software, Coolants, Modeling, Nuclear power stations, Pressure, Pressure vessels
Proceedings Papers

Analysis on Flow Behavior in the Plenum of RPV of PWR

Lei Huang, Lu-lu Hao, Hong Chen, Jun-feng Xue, Li-li Tong
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81547
https://doi.org/10.1115/ICONE26-81547
View Paper titled, Analysis on Flow Behavior in the Plenum of RPV of PWR
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Topics: Flow (Dynamics), Pressurized water reactors, Coolants, Eddies (Fluid dynamics), Angular momentum, Computational fluid dynamics, Cylinders, Design, Pipes, Pressure
Proceedings Papers

Sensitivity Analysis of Turbulence Models for the Core Inlet Flow Distribution of PWR

Lu-lu Hao, Hong Chen, Su chen Qiu
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A047, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82454
https://doi.org/10.1115/ICONE26-82454
View Paper titled, Sensitivity Analysis of Turbulence Models for the Core Inlet Flow Distribution of PWR
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Topics: Flow (Dynamics), Pressurized water reactors, Sensitivity analysis, Turbulence, Simulation, Computation, Computational fluid dynamics, Geometry, Mesh generation, Computer software
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81694
https://doi.org/10.1115/ICONE26-81694
View Paper titled, Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark
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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams
Proceedings Papers

Control Strategy Investigation for a Multi-Purpose Modular Small Pressurized Water Reactor With Once-Through Steam Generators

Qian Ma, Peiwei Sun
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81318
https://doi.org/10.1115/ICONE26-81318
View Paper titled, Control Strategy Investigation for a Multi-Purpose Modular Small Pressurized Water Reactor With Once-Through Steam Generators
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Topics: Boilers, Pressurized water reactors, Feedwater, Flow (Dynamics), Steam, Stress, Turbines, Coolants, Pressure vessels, China
Proceedings Papers

A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

Noriaki Hirota, Atsuhiko Terada, Xing L. Yan, Kohei Tanaka, Akihito Otani
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81718
https://doi.org/10.1115/ICONE26-81718
View Paper titled, A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System
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Topics: Combined heat and power, Heat exchangers, High temperature, Hydrogen, Nuclear reactors, Conceptual design, Design, Gas turbines, Construction, Creep