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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
Paper No: ICONE29-89495
DOI: https://doi.org/10.1115/ICONE29-89495
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Topics: China, Control systems, Design, Heat pipes, Nuclear engineering, Pipes, Predictive control, Pressure vessels
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
Paper No: ICONE29-93545
DOI: https://doi.org/10.1115/ICONE29-93545
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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
Paper No: ICONE29-89228
DOI: https://doi.org/10.1115/ICONE29-89228
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Topics: Accidents, Boron, Flow (Dynamics), Fluids, Reactor vessels, Water, Pressure vessels, Coolants, Safety, Fluid dynamics
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
Paper No: ICONE29-92039
DOI: https://doi.org/10.1115/ICONE29-92039
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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

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
Paper No: ICONE29-93082
DOI: https://doi.org/10.1115/ICONE29-93082
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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

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
Paper No: ICONE29-90217
DOI: https://doi.org/10.1115/ICONE29-90217
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Topics: Electromagnets, Motion control, Design, Pressure vessels, Actuators, Artificial intelligence, Engineering prototypes, Engines, Gravity (Force), Helium
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
Paper No: ICONE28-65689
DOI: https://doi.org/10.1115/ICONE28-65689
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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
Paper No: ICONE28-65770
DOI: https://doi.org/10.1115/ICONE28-65770
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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
Paper No: ICONE2020-16035
DOI: https://doi.org/10.1115/ICONE2020-16035
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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
Paper No: ICONE2020-16650
DOI: https://doi.org/10.1115/ICONE2020-16650
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Topics: Fatigue, Flow-induced vibrations, Fluids, Pressure vessels, Random vibration, Risk assessment
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
Paper No: ICONE26-81263
DOI: https://doi.org/10.1115/ICONE26-81263
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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
Paper No: ICONE26-81547
DOI: https://doi.org/10.1115/ICONE26-81547
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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
Paper No: ICONE26-82454
DOI: https://doi.org/10.1115/ICONE26-82454
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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

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
Paper No: ICONE26-82135
DOI: https://doi.org/10.1115/ICONE26-82135
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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

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
Paper No: ICONE26-81694
DOI: https://doi.org/10.1115/ICONE26-81694
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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
Paper No: ICONE26-81318
DOI: https://doi.org/10.1115/ICONE26-81318
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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
Paper No: ICONE26-81718
DOI: https://doi.org/10.1115/ICONE26-81718
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Topics: Combined heat and power, Heat exchangers, High temperature, Hydrogen, Nuclear reactors, Conceptual design, Design, Gas turbines, Construction, Creep
Proceedings Papers

Approach to UK SMR Component Design

Christopher D. Bell
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, V001T13A003, July 22–26, 2018
Paper No: ICONE26-81188
DOI: https://doi.org/10.1115/ICONE26-81188
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Topics: Design, Inspection, Manufacturing, Safety, Carbon, Design for Manufacturing, Energy generation, Failure, Failure mechanisms, Nuclear power stations
Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Paper No: ICONE26-81096
DOI: https://doi.org/10.1115/ICONE26-81096
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Application of Similarity Law in Electrical Device Design in Helium for High Temperature Gas-Cooled Reactor

Xiaohuan Chen, Yinan Geng, Jie Wang
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A029, July 22–26, 2018
Paper No: ICONE26-82520
DOI: https://doi.org/10.1115/ICONE26-82520
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Topics: Design, Helium, Very high temperature reactors, Pressure, High pressure (Physics), Insulation, China, Electrical components, Engineering prototypes, Finite element methods