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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

ICONE29 Front Matter

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T00A001, August 8–12, 2022

Paper No: ICONE29-FM15

DOI: https://doi.org/10.1115/ICONE29-FM15

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Proceedings Papers

Comprehensive Comparison and Analysis for Fast Reactors

Zheng Yan, Weiguang Zhao, Xiaxin Cao, Changqi Yan

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A006, August 8–12, 2022

Paper No: ICONE29-90528

DOI: https://doi.org/10.1115/ICONE29-90528

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Topics: Fast neutron reactors, Fuels

Proceedings Papers

Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

Hidemasa Yamano, Satoshi Futagami, Masanori Ando

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A034, August 8–12, 2022

Paper No: ICONE29-93231

DOI: https://doi.org/10.1115/ICONE29-93231

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Topics: Deformation, High temperature, Reactor vessels, Resilience, Sodium fast reactors, Structural analysis

Proceedings Papers

Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition

Kun Cheng, Xiao Chu, Zhifang Qiu, Lin Xian, Jian Deng

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A023, August 8–12, 2022

Paper No: ICONE29-92063

DOI: https://doi.org/10.1115/ICONE29-92063

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Topics: Nuclear reactors, Oceans

Proceedings Papers

Heating Start-Up Method and Demonstration for Full Natural Circulation Reactor

Jianhui Yu, Wenji Tan, Xingliang Zhang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A013, August 8–12, 2022

Paper No: ICONE29-91535

DOI: https://doi.org/10.1115/ICONE29-91535

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Topics: Heating

Proceedings Papers

Volume Change Analysis of Primary Loop in a Small Modular Thorium-Based Molten Salt Reactor

Guifeng Zhu, Yang Zou, Rui Yan, Wei Guo, Xuzhong Kang, Tiangui Xu, Pu Yang, Bo Zhou

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A004, August 8–12, 2022

Paper No: ICONE29-90295

DOI: https://doi.org/10.1115/ICONE29-90295

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Topics: Containment, Graphite, Molten salt reactors, Thermal expansion

Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022

Paper No: ICONE29-93244

DOI: https://doi.org/10.1115/ICONE29-93244

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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)

Proceedings Papers

The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method

Weiquan Yuan, Zhao Chen, Kangli Shi, Chang Su, Jinghua Tang, Dawei Cui, Chengjie Duan

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A024, August 8–12, 2022

Paper No: ICONE29-92077

DOI: https://doi.org/10.1115/ICONE29-92077

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Topics: Fast neutron reactors

Proceedings Papers

Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

Mao Yujia, Sheng Liyuan, Yang Ruobing, Bai Wei, Li Jing

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A014, August 8–12, 2022

Paper No: ICONE29-91546

DOI: https://doi.org/10.1115/ICONE29-91546

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Topics: Design, Drainage, Water

Proceedings Papers

Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor

Jinggang Xu, Qin Zeng, Sheng Wang, Huaihuai Wang, Junjie Zhou, Yangbin Xiong, Jingchen Yang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A007, August 8–12, 2022

Paper No: ICONE29-90643

DOI: https://doi.org/10.1115/ICONE29-90643

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Topics: Magnetic fusion, Modeling, Nuclear fuel cycle

Proceedings Papers

Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with a Single Particle

Hanyang Lyu, Xiang Wang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A028, August 8–12, 2022

Paper No: ICONE29-92564

DOI: https://doi.org/10.1115/ICONE29-92564

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Topics: Particulate matter, Plasmas (Ionized gases), Simulation

Proceedings Papers

Experimental Study on Measurement Characteristics of Different Type Flow Meters in Pb-Bi Environment

Xin Liu, Xiangyu Yun, Junming Liang, HuiYong Zhang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A015, August 8–12, 2022

Paper No: ICONE29-91675

DOI: https://doi.org/10.1115/ICONE29-91675

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Topics: Flow (Dynamics), Flowmeters

Proceedings Papers

Optimization of Core Parameters Based on Artificial Neural Network Surrogate Model

Shu Chen, Peng Ding, Shuowen Hu, Wenqing Xia, Min Liu, Fengwan Yu, Wenhuai Li

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A005, August 8–12, 2022

Paper No: ICONE29-90511

DOI: https://doi.org/10.1115/ICONE29-90511

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Topics: Artificial neural networks, Optimization

Proceedings Papers

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A026, August 8–12, 2022

Paper No: ICONE29-92284

DOI: https://doi.org/10.1115/ICONE29-92284

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Topics: Heat, Molten salt reactors, Numerical analysis

Proceedings Papers

Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

Yuichi Onoda, Masato Uchita, Minako Tokizaki, Hitoshi Okazaki

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A016, August 8–12, 2022

Paper No: ICONE29-91688

DOI: https://doi.org/10.1115/ICONE29-91688

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Topics: Pumps, Rupture, Safety, Signals, Sodium fast reactors

Proceedings Papers

Corrosion Behavior of Zr-0.75Sn-0.35Fe-0.15Cr- x Nb Alloys in Oxygen-Containing Super-Heated Steam at 400 °C

Meiyi Yao, Shitong Xu, Wen Pei, Lijuan Hu, Xiaodong Lin, Yaoping Xie, Jianchao Peng, Xue Liang, Bangxin Zhou

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A009, August 8–12, 2022

Paper No: ICONE29-91231

DOI: https://doi.org/10.1115/ICONE29-91231

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Topics: Corrosion, Niobium alloys, Oxygen, Steam, Superheating, Zirconium, Zirconium alloys

Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022

Paper No: ICONE29-94534

DOI: https://doi.org/10.1115/ICONE29-94534

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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization

Proceedings Papers

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

Xiaolin Chen, Simon Li, Songbai Cheng

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022

Paper No: ICONE29-92109

DOI: https://doi.org/10.1115/ICONE29-92109

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Topics: Accidents, Flow (Dynamics), Sodium fast reactors, Three-dimensional models, Transients (Dynamics)

Proceedings Papers

A Drive-Through Passenger Vehicle Inspecting System Using X-Ray Digital Radiography

Jianmin Tong, Yibin Huang, Xiaojing Guo, Liu Chen, Peng Cong, Zhentao Wang, Guilai Xing, Liqiang Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A067, August 8–12, 2022

Paper No: ICONE29-93780

DOI: https://doi.org/10.1115/ICONE29-93780

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Topics: Vehicles, X-rays

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NARROW

ICONE29 Front Matter

Comprehensive Comparison and Analysis for Fast Reactors

Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition

Heating Start-Up Method and Demonstration for Full Natural Circulation Reactor

Volume Change Analysis of Primary Loop in a Small Modular Thorium-Based Molten Salt Reactor

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method

Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor

Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with a Single Particle

Experimental Study on Measurement Characteristics of Different Type Flow Meters in Pb-Bi Environment

Optimization of Core Parameters Based on Artificial Neural Network Surrogate Model

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

Corrosion Behavior of Zr-0.75Sn-0.35Fe-0.15Cr- x Nb Alloys in Oxygen-Containing Super-Heated Steam at 400 °C

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

A Drive-Through Passenger Vehicle Inspecting System Using X-Ray Digital Radiography

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