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Proceedings Papers

Research on the Localization Method of Loose Components in Nuclear Power Plants Based on Hilbert-Huang Signal Processing

Jiming Jiang, Yu Liu, Daogang Lu
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A022, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135066
https://doi.org/10.1115/ICONE31-135066
View Paper titled, Research on the Localization Method of Loose Components in Nuclear Power Plants Based on Hilbert-Huang Signal Processing
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Topics: Monitoring systems, Nuclear power stations, Signal processing, Signals, Circuits, Failure, Algorithms, Building renovation, Collisions (Physics), Construction
Proceedings Papers

Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN

Hongwei Jiang, Guangliang Chen, Zhaofei Tian
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A048, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134838
https://doi.org/10.1115/ICONE31-134838
View Paper titled, Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN
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Topics: Computational fluid dynamics, Computer simulation, Coolants, Design, Flow (Dynamics), Fuel cells, Fuel rods, Fuels, Pressurized water reactors, Resolution (Optics)
Proceedings Papers

The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme

Songyang Liu, Xuelin Li, Yong Luo, Wei Liu, Qin Zhou, Cheng Gu, Tian Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133310
https://doi.org/10.1115/ICONE31-133310
View Paper titled, The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
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Topics: Accidents, Steady state, Fuels, Temperature, China, Equilibrium (Physics), Graphite, Construction, Coolants, Design
Proceedings Papers

Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor

Jipu Hu, Yuyang Shen, Ruixiang Wang, Kuaiyuan Feng, Lei Lou, Hui Guo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-124442
https://doi.org/10.1115/ICONE31-124442
View Paper titled, Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor
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Topics: Accidents, Ceramics, Computer software, Coolants, Design, Engineering simulation, Flow (Dynamics), Fluids, Fuels, Graphite
Proceedings Papers

Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core

Guihua Lai, Tian Wang, Ding She, Hong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135206
https://doi.org/10.1115/ICONE31-135206
View Paper titled, Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
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Topics: Conceptual design, Fast neutron reactors, Small modular reactors, Supercritical carbon dioxide, Safety, Temperature, Design, Fuel rods, Heat, Particulate matter
Proceedings Papers

Effect of the Heat Transfer Correlation Choice on the Coupled Assessment of Energy Release and Stress-Strain State of an Elementary Supercritical Fuel Rod Under Nuclear Heating Conditions

Vladislav Filonov, Oleksandr Kovalenko, Yaroslav Dubyk, Yuliia Filonova, Dmitriy Fedorov
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A069, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136275
https://doi.org/10.1115/ICONE31-136275
View Paper titled, Effect of the Heat Transfer Correlation Choice on the Coupled Assessment of Energy Release and Stress-Strain State of an Elementary Supercritical Fuel Rod Under Nuclear Heating Conditions
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Topics: Approximation, Diffusion (Physics), Fuel rods, Heat transfer, Heating, Stress, Temperature, Design, Fuels, Computational fluid dynamics
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
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Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

The Experimental Research of Integrative SMR Using TEG for Power Generation

Suhao Wang, Yong Li, Hui Xiao, Liang Guo, Ying Li, Ruifan Lou, Hairong Tang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133679
https://doi.org/10.1115/ICONE31-133679
View Paper titled, The Experimental Research of Integrative SMR Using TEG for Power Generation
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Topics: Coolants, Design, Energy conversion, Energy generation, Generators, Heat, High temperature, Industrial research, Liquid metals, Optimization
Proceedings Papers

Comparison of K-Solutions of Rectangular Flaw With Semi-Elliptical Flaw for PWSCC Growth Analysis

Kiminobu Hojo, David Rudland
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136517
https://doi.org/10.1115/ICONE31-136517
View Paper titled, Comparison of K-Solutions of Rectangular Flaw With Semi-Elliptical Flaw for PWSCC Growth Analysis
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Topics: ASME Standards, Coolants, Fracture (Materials), Japan Society of Mechanical Engineers, JSME Standards, Metals, Pipes, Shapes, Stress corrosion cracking, Surges
Proceedings Papers

Development of a Qualified Plant Nodalization for Steady State and Transient Analysis of Table Top Facility

Davide Rozzia, Loukas Dikonimos Makris, Jan Cools, Tom Van Loy, Tim Verpoorten, Katrien Van Tichelen
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A107, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136859
https://doi.org/10.1115/ICONE31-136859
View Paper titled, Development of a Qualified Plant Nodalization for Steady State and Transient Analysis of Table Top Facility
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Topics: Steady state, Transient analysis, Coolants, Hydraulic drive systems, Leakage, Heating, Helium, Water, Design, Flow (Dynamics)
Proceedings Papers

Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core

Minyang Gui, Di Wu, Hangyuan Zhang, Senmiao Zhang, Hui Cheng
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A106, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136580
https://doi.org/10.1115/ICONE31-136580
View Paper titled, Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core
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Topics: Cladding systems (Building), Coolants, Fast neutron reactors, Flow (Dynamics), Gravity (Force), Manufacturing, Nuclear power stations, Power density, Safety, Temperature
Proceedings Papers

Experimental Study of Heat Transfer Characteristics During Reflooding Process Under Partially Exposed Conditions in Narrow Rectangular Channels

Junchen Wu, Haidong Liu, Deqi Chen, Qianlong Zuo, Hanzhou Liu, Jian Deng, Dan Wu, Mingjing Chen
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A093, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136011
https://doi.org/10.1115/ICONE31-136011
View Paper titled, Experimental Study of Heat Transfer Characteristics During Reflooding Process Under Partially Exposed Conditions in Narrow Rectangular Channels
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Topics: Accidents, Boiling, Coolants, Cooling, Film boiling, Flow (Dynamics), Fuels, Heat transfer, Heat transfer coefficients, Nuclear reactors
Proceedings Papers

Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method

Mingqian Zhang, Run Lin
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132452
https://doi.org/10.1115/ICONE31-132452
View Paper titled, Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method
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Topics: Computational fluid dynamics, Coolants, Domes (Structural elements), Nuclear reactor coolants, Pressurized water reactors, Simulation, Swirling flow, Thermal hydraulics, Pumps, Reactor vessels
Proceedings Papers

Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation

Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134796
https://doi.org/10.1115/ICONE31-134796
View Paper titled, Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation
Open the PDF for Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation in another window
Topics: Fast neutron reactors, Stainless steel, Coolants, Temperature, Accidents, Pressure, Safety, Sodium, Temperature distribution, Vessels
Proceedings Papers

CFD Analysis of a Four-Loop Pressurized Water Reactor With Multiple Operating Conditions

Yizhi Tian, Guangliang Chen, Ruojun Xue, Yuchen Sun, Jinchao Li, Rui Li
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134682
https://doi.org/10.1115/ICONE31-134682
View Paper titled, CFD Analysis of a Four-Loop Pressurized Water Reactor With Multiple Operating Conditions
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Topics: Computational fluid dynamics, Coolants, Flow (Dynamics), Porous materials, Pressurized water reactors
Proceedings Papers

Evaluation of Coolant Mixing Characteristics in the Lower Plenum of a Scaled PWR With OpenFOAM

Lilia Djebara, Hongyang Wei, Cheng Yang, Sichao Tan, Ruifeng Tian
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134558
https://doi.org/10.1115/ICONE31-134558
View Paper titled, Evaluation of Coolant Mixing Characteristics in the Lower Plenum of a Scaled PWR With OpenFOAM
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Topics: Coolants, Pressurized water reactors
Proceedings Papers

Analytical Study of Melt Spreading in Shallow Pool Observed in PULiMS-E10 Test Using MSPREAD Implemented With Molten Jet Quench Model

Wataru Kikuchi, Akitoshi Hotta, Koetsu Ito, Hiroaki Yugo, Mamoru Shimizu
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A046, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135902
https://doi.org/10.1115/ICONE31-135902
View Paper titled, Analytical Study of Melt Spreading in Shallow Pool Observed in PULiMS-E10 Test Using MSPREAD Implemented With Molten Jet Quench Model
Open the PDF for Analytical Study of Melt Spreading in Shallow Pool Observed in PULiMS-E10 Test Using MSPREAD Implemented With Molten Jet Quench Model in another window
Topics: Chain, Computer simulation, Coolants, Cooling, Heat transfer, Resolution (Optics), Sensitivity analysis, Shapes, Slug flows, Water
Proceedings Papers

Geometric Uncertainty Analysis of Fuel Assembly Based on Sub-Channel Model

Deyan Kong, Zhibo Gao, Di Wu, Jie Cheng, Jianjun Wang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131992
https://doi.org/10.1115/ICONE31-131992
View Paper titled, Geometric Uncertainty Analysis of Fuel Assembly Based on Sub-Channel Model
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Topics: Fuels, Manufacturing, Uncertainty, Uncertainty analysis, Fuel rods, Temperature, Coolants, Pressurized water reactors, Machining, Rods
Proceedings Papers

SIMMER-III Code Simulation of High-Pressure Water-Lead Interaction in Westinghouse’s LEWIN Test Facility

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Fabio Martini, Sung Jin Lee, Mariano Tarantino, Francesco Galleni, Andrea Pucciarelli, Alessio Pesetti
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136222
https://doi.org/10.1115/ICONE31-136222
View Paper titled, SIMMER-III Code Simulation of High-Pressure Water-Lead Interaction in Westinghouse’s LEWIN Test Facility
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Topics: Coolants, High pressure (Physics), Simulation, Test facilities, Water
Proceedings Papers

Development of DLOFC Accident Analysis Function of DAYU

Haoming Dou, Minggang Lang, Ding She, Han Zhang
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A028, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134550
https://doi.org/10.1115/ICONE31-134550
View Paper titled, Development of DLOFC Accident Analysis Function of DAYU
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Topics: Accidents, Flow (Dynamics), Very high temperature reactors, Coolants, Pressure, Circuits, Design, Temperature, Cooling, Dynamics (Mechanics)