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Proceedings Papers

Research on Dynamic Rod Measurement Method Based on Torch Software Package for PWR

Yun Cai, TianYa Li, Rui Guo, Tongxian Liu, Qing Li, LingFang Yang, Wenbo Zhao
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A026, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135284
https://doi.org/10.1115/ICONE31-135284
View Paper titled, Research on Dynamic Rod Measurement Method Based on Torch Software Package for PWR
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Topics: Computer software, Pressurized water reactors, Spacetime, Neutrons, China, Electricity (Physics), Errors, Nuclear power, Physics, Power stations
Proceedings Papers

Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply

Oleksandr Mazurok, Valeriy Zuyok, Vadym Ivanov, Mykhaylo Tretyakov
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134916
https://doi.org/10.1115/ICONE31-134916
View Paper titled, Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply
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Topics: Absorption, Boron, Cladding systems (Building), Density, Dysprosium, Europium, Fuels, Hafnium, Neutrons, Nuclear power stations
Proceedings Papers

Control Rod Cooperative Control Strategy Based on Multipoint Reactor Model

Bowen Tu, Airan Dang, Xiuchun Luan
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135073
https://doi.org/10.1115/ICONE31-135073
View Paper titled, Control Rod Cooperative Control Strategy Based on Multipoint Reactor Model
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Topics: Delays, Fuzzy control, Rods, Safety, Simulation results
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

Study on Parameters Design Methodology for Rolling and Pitching Test of Control Rod Hydraulic Drive System

Yanlin Li, Benke Qin, Hanliang Bo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130895
https://doi.org/10.1115/ICONE31-130895
View Paper titled, Study on Parameters Design Methodology for Rolling and Pitching Test of Control Rod Hydraulic Drive System
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Topics: Design methodology, Hydraulic drive systems, Rods, Stress, Accidents, Design, Fluids, Heating, Marine engineering, Naval architecture
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

Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark

Yuan Yuan, Guoming Liu, Peng Zhang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135368
https://doi.org/10.1115/ICONE31-135368
View Paper titled, Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark
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Topics: Neutrons, Nuclear design, Uncertainty, Very high temperature reactors, Cross section (Physics), Fuels, Modeling, Rods
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

Determination of Control Rod Position by Global Optimization Methods

Zhang Qian, Zhihong Liu, Jing Zhao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A100, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92637
https://doi.org/10.1115/ICONE29-92637
View Paper titled, Determination of Control Rod Position by Global Optimization Methods
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Topics: Algorithms, Optimization, Pressurized water reactors, Sensors, Computer software, Genetic algorithms, Inverse problems, Neutrons, Particle swarm optimization, Physics
Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92788
https://doi.org/10.1115/ICONE29-92788
View Paper titled, A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs
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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)
Proceedings Papers

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90296
https://doi.org/10.1115/ICONE29-90296
View Paper titled, Application of the Refinement Spacer Grid Model in Subchannel Analysis Code
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Topics: Axial flow, Economics , Flow (Dynamics), Fluids, Friction, Fuel rods, Momentum, Particulate matter, Pressurized water reactors, Rods
Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89917
https://doi.org/10.1115/ICONE29-89917
View Paper titled, Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Yifeng Hu, Zhiqiang Hu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91474
https://doi.org/10.1115/ICONE29-91474
View Paper titled, Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines
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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling
Proceedings Papers

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Wei Li, Jianfeng Shi, Yulong Qin, Lihua Wang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A047, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92633
https://doi.org/10.1115/ICONE29-92633
View Paper titled, Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods
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Topics: Feedwater, Pumps, Rods, Nuclear power stations, Turbines
Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89461
https://doi.org/10.1115/ICONE29-89461
View Paper titled, Research on the Influence of Degassing on the Release of Fission Gases in PWRs
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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods
Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93095
https://doi.org/10.1115/ICONE29-93095
View Paper titled, Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures
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Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers
Proceedings Papers

Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor

Haojie Zhang, Yanhua Zheng, Ding She, Lei Shi
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A057, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91754
https://doi.org/10.1115/ICONE29-91754
View Paper titled, Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor
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Topics: Rods, Very high temperature reactors
Proceedings Papers

Alternative Absorber Materials for Control Rods in ALFRED

Hui Guo, Xin Jin, Kuaiyuan Feng, Hanyang Gu
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, V001T03A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61123
https://doi.org/10.1115/ICONE28-61123
View Paper titled, Alternative Absorber Materials for Control Rods in ALFRED
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Topics: Fast neutron reactors, Rods
Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto
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, V001T04A010, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64347
https://doi.org/10.1115/ICONE28-64347
View Paper titled, A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations
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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature
Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66591
https://doi.org/10.1115/ICONE28-66591
View Paper titled, Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux