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Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022
Paper No: ICONE29-92103
DOI: https://doi.org/10.1115/ICONE29-92103
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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results
Proceedings Papers

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

Li Jiang, Jianqiang Shan
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A038, August 8–12, 2022
Paper No: ICONE29-93217
DOI: https://doi.org/10.1115/ICONE29-93217
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Topics: Fuel rods, Pressurized water reactors, Turbulence, Two-phase flow, Critical heat flux, Axial flow, Convection, Fluids, Pipes, Temperature
Proceedings Papers

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Wang Kai, Ming Jia Zhou, Wei Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A037, August 8–12, 2022
Paper No: ICONE29-91242
DOI: https://doi.org/10.1115/ICONE29-91242
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Topics: Automatic control, Control systems, Cooling, Design, Heating, Heating and cooling, Nuclear power stations, Pressure, Simulation, Temperature
Proceedings Papers

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022
Paper No: ICONE29-89165
DOI: https://doi.org/10.1115/ICONE29-89165
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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design
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

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022
Paper No: ICONE29-93417
DOI: https://doi.org/10.1115/ICONE29-93417
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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis
Proceedings Papers

An Insulation Structure With Noise Reduction Function

Zhang Yicheng, Bian Pengfei, Zhang Kai
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A069, August 8–12, 2022
Paper No: ICONE29-93144
DOI: https://doi.org/10.1115/ICONE29-93144
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Topics: Acoustics, Insulation, Noise control, Thermal insulation, Nuclear power, Acoustical materials, Glass, Pipelines, Damping, Density
Proceedings Papers

Development and Validation of a New Gas Conductance Model

Shengzhi Yang, Xiaoyan Wei, Yanan Zhu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A038, August 8–12, 2022
Paper No: ICONE29-91758
DOI: https://doi.org/10.1115/ICONE29-91758
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Topics: Electrical conductance, Temperature
Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022
Paper No: ICONE29-90521
DOI: https://doi.org/10.1115/ICONE29-90521
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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors
Proceedings Papers

Study on Water Chemistry and Temperature Adaptability of CZ Zirconium Alloy

Hansen Chen, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A090, August 8–12, 2022
Paper No: ICONE29-93820
DOI: https://doi.org/10.1115/ICONE29-93820
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Topics: Temperature, Water chemistry, Zirconium alloys
Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022
Paper No: ICONE29-93816
DOI: https://doi.org/10.1115/ICONE29-93816
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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter
Proceedings Papers

Extraction of Nd(III), Eu(III), Am(III) and Cm(III) With 6-Carboxylic Di(2-Ethylhexyl) Amide Pyridine

Chao Xu, Yu Du, Tingting Liu, Suliang Yang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A024, August 8–12, 2022
Paper No: ICONE29-90818
DOI: https://doi.org/10.1115/ICONE29-90818
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Topics: Atoms, Cycles, Design, Equilibrium (Physics), Infrared spectra, Ion exchange, Mass transfer, Separation (Technology), Spent nuclear fuels, Temperature
Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022
Paper No: ICONE29-90736
DOI: https://doi.org/10.1115/ICONE29-90736
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Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants
Proceedings Papers

Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(III)

Cong Mao, Hongji Sang, Jiawei Zheng, Yan Wu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A077, August 8–12, 2022
Paper No: ICONE29-93196
DOI: https://doi.org/10.1115/ICONE29-93196
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Topics: Composite materials, Fittings, Metals, Sewage, Temperature, Water, Zirconium
Proceedings Papers

Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II

Canxing Huang, Huasheng Xiong, Junting Feng
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A014, August 8–12, 2022
Paper No: ICONE29-91509
DOI: https://doi.org/10.1115/ICONE29-91509
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Topics: Accidents, Boilers, Control systems, Coolants, Heating, Nuclear power, Pressurized water reactors, Pumps, Radioactivity, Safety
Proceedings Papers

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

William A. Byers, Guoqiang Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A094, August 8–12, 2022
Paper No: ICONE29-94477
DOI: https://doi.org/10.1115/ICONE29-94477
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Topics: Cladding systems (Building), Zirconium, Corrosion, Coating processes, Coatings, Fuels, Pressurized water reactors, Accidents, Boiling, Boron
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

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Peng Yuan, Jian Deng, Zhifang Qiu, Qinglan Xu, Dahuan Zhu, Tao Huang, Zhongchun Li, Peng Du
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A006, August 8–12, 2022
Paper No: ICONE29-92380
DOI: https://doi.org/10.1115/ICONE29-92380
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Topics: Accidents, Algorithms, Artificial neural networks, China, Coolants, Design, Flow (Dynamics), Machine learning, Nuclear power stations, Nuclear reactors
Proceedings Papers

Numerical Analysis of Heat Transfer Enhancement With Spiral Tube in the Passive Containment System

Kai Chen, Ruiqi Wang, Chonghai Huang, Xiao Qi, Xiaoyan Wang
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A002, August 8–12, 2022
Paper No: ICONE29-88875
DOI: https://doi.org/10.1115/ICONE29-88875
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Topics: Condensation, Containment systems, Heat transfer, Numerical analysis, Steam, Vapors, Heat, Liquid films, Pressure, Temperature
Proceedings Papers

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Xinyue Luo, Daogang Lu, Jiaqi Feng, Yuhao Zhang
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A040, August 8–12, 2022
Paper No: ICONE29-92323
DOI: https://doi.org/10.1115/ICONE29-92323
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Topics: Heat transfer, Radiation (Physics), Sodium fast reactors, Cavities, Fast neutron reactors, Temperature, Vessels, Computational fluid dynamics, Construction, Containers