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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

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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

The Experimental Research of Integrative SMR Using TEG for Power Generation

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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

Preliminary Design and Transient Simulation of a Nuclear-Solar Hybrid System Using an Open-Air Brayton Cycle

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Jiaolong Deng, Chaoran Guan, Xiaojing Liu, Hui He, Xiang Chai
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135136
https://doi.org/10.1115/ICONE31-135136
View Paper titled, Preliminary Design and Transient Simulation of a Nuclear-Solar Hybrid System Using an Open-Air Brayton Cycle
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Topics: Brayton cycle, Concentrating solar power, Design, Heat, Nuclear reactors, Pipes, Simulation, Solar energy, Thermal energy storage, Transients (Dynamics)
Proceedings Papers

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

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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

Research of Supercritical Carbon Dioxide Thermal Power System Based on Lead-Cooled Fast Reactor

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Zhihui Li, Chunyuan Liu, Mian Xing, Gang Zheng, Yu Wang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90432
https://doi.org/10.1115/ICONE29-90432
View Paper titled, Research of Supercritical Carbon Dioxide Thermal Power System Based on Lead-Cooled Fast Reactor
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Topics: Brayton cycle, Compression, Fast neutron reactors, Supercritical carbon dioxide, Thermal energy
Proceedings Papers

Validation of TULIP via ICSBEP Critical Benchmark

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Wenjie Chen, Xianan Du, Youqi Zheng, Yongping Wang, Rong Wang, Hongchun Wu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A113, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93353
https://doi.org/10.1115/ICONE29-93353
View Paper titled, Validation of TULIP via ICSBEP Critical Benchmark
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Topics: Computational physics, Cross section (Physics), Design, Doppler effect, Feedback, Manufacturing, Neutrons, Nuclear design, Nuclear engineering, Nuclear fission
Proceedings Papers

Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR

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Yanfei Qiu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A033, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93201
https://doi.org/10.1115/ICONE29-93201
View Paper titled, Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR
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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors
Proceedings Papers

Nuclear Cognition and Public Acceptance

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Weiqiang Zhu, Peng Wang, Changying Fu
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91416
https://doi.org/10.1115/ICONE29-91416
View Paper titled, Nuclear Cognition and Public Acceptance
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Topics: Carbon, Innovation, Leakage, Nuclear power, Radioactivity, Renewable energy, Risk, Safety, Sustainable development, Thermal energy
Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

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Yun Feng, Pei-Wei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92872
https://doi.org/10.1115/ICONE29-92872
View Paper titled, Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor
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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)
Proceedings Papers

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

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Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang
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, V001T02A020, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64532
https://doi.org/10.1115/ICONE28-64532
View Paper titled, A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform
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Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design
Proceedings Papers

Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming

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Junyi Li, Zhe Dong, Bowen Li
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A030, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64344
https://doi.org/10.1115/ICONE28-64344
View Paper titled, Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming
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Topics: Dynamic modeling, Hydrogen production, Methane, Steam reforming, Molten salt reactors, Steam, Thermal energy, Catalysts, Coolants, Electric power generation
Proceedings Papers

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

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Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng
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, V001T04A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63220
https://doi.org/10.1115/ICONE28-63220
View Paper titled, Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D
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Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants
Proceedings Papers

Neutronic Study on Conceptual Lithium Fluoride Salt Cooled Fusion Driven System for Actinide Transmutation

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Feryantama Putra
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, V001T05A011, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16368
https://doi.org/10.1115/ICONE2020-16368
View Paper titled, Neutronic Study on Conceptual Lithium Fluoride Salt Cooled Fusion Driven System for Actinide Transmutation
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Topics: Lithium, Coolants, Design, Fuel rods, Neutron sources, Chain, Combustion, Cycles, Fast neutron reactors, Fuels
Proceedings Papers

Synergy of an SMR for Addressing Remote Communities Non-Nuclear Waste

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Glenn Harvel
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A013, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16671
https://doi.org/10.1115/ICONE2020-16671
View Paper titled, Synergy of an SMR for Addressing Remote Communities Non-Nuclear Waste
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Topics: Central heating, Diesel, Fossil fuels, Fuels, Heat, Heating, Plastics, Pyrolysis, Stress, Thermal energy
Proceedings Papers

A Simulation of Small Break Loss of Coolant Accident in Nuclear Heating Reactor Based on RELAP5

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Meng Lu, Heng Xie
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A036, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81416
https://doi.org/10.1115/ICONE26-81416
View Paper titled, A Simulation of Small Break Loss of Coolant Accident in Nuclear Heating Reactor Based on RELAP5
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Topics: Accidents, Coolants, Heating, Simulation, Heat, Safety, Light water reactors, Pumps, Reactor vessels, Thermal energy
Proceedings Papers

Assessment of RELAP/SCDAPSIM for Turbine Trip Transient in NuScale-SMR

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Katarzyna Skolik, Anuj Trivedi, Marina Perez-Ferragut, Chris Allison
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81861
https://doi.org/10.1115/ICONE26-81861
View Paper titled, Assessment of RELAP/SCDAPSIM for Turbine Trip Transient in NuScale-SMR
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Topics: Transients (Dynamics), Turbines, Fuels, Pressurized water reactors, Accidents, Boilers, Containment, Coolants, Design, Flow (Dynamics)
Proceedings Papers

Investigation on Thermal-Hydraulic Parameters and Instability Under Two Different Heating Conditions Based on RELAP5 Code

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Zhaoyang Xia, Zhiwei Zhou, Tianji Peng
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A048, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82268
https://doi.org/10.1115/ICONE26-82268
View Paper titled, Investigation on Thermal-Hydraulic Parameters and Instability Under Two Different Heating Conditions Based on RELAP5 Code
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Topics: Heating, Heat transfer, Critical heat flux, Heat, Superheating, Boilers, Density, Energy generation, Fluid dynamics, Oscillations
Proceedings Papers

Validation of Film Evaporation Model in GASFLOW-MPI

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Li Yabing, Zhang Han, Xiao Jianjun
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A003, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81249
https://doi.org/10.1115/ICONE26-81249
View Paper titled, Validation of Film Evaporation Model in GASFLOW-MPI
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Topics: Evaporation, Containment, Heat, Wall temperature, Air flow, Computational fluid dynamics, Cooling systems, Heating, Nuclear power stations, Safety
Proceedings Papers

Integrated Design of a Reactor Core for the Rolls-Royce Small Modular Reactor Project

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Simon de Haas, David Chu, Kevin Ellis, Matthew White, Ben Lindley, Peter Smith, Julian Murgatroyd, Andrew Grief, Mike Leddy, Mike Yule
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, V001T13A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81311
https://doi.org/10.1115/ICONE26-81311
View Paper titled, Integrated Design of a Reactor Core for the Rolls-Royce Small Modular Reactor Project
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Topics: Design, Small modular reactors, Safety, Cycles, Corporate average fuel economy, Engineering disciplines, Fuel efficiency, Fuels, Physics, Power stations
Proceedings Papers

Heat Transfer to Supercritical Water (Liquid-Like State) Flowing in a Short Vertical Bare Tube With Upward Flow

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A. Zvorykin, M. Mahdi, R. Popov, K. Barati Far, I. Pioro
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A038, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81608
https://doi.org/10.1115/ICONE26-81608
View Paper titled, Heat Transfer to Supercritical Water (Liquid-Like State) Flowing in a Short Vertical Bare Tube With Upward Flow
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Topics: Flow (Dynamics), Heat transfer, Water, Nuclear power stations, Thermal efficiency, Supercritical water reactors, Thermal power stations, Coal, Combined cycles, Cooling