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Proceedings Papers

Nuclear Cognition and Public Acceptance

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A007, August 8–12, 2022

Paper No: ICONE29-91416

DOI: https://doi.org/10.1115/ICONE29-91416

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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

Yun Feng, Pei-Wei Sun, Xinyu Wei

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022

Paper No: ICONE29-92872

DOI: https://doi.org/10.1115/ICONE29-92872

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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)

Proceedings Papers

Validation of TULIP via ICSBEP Critical Benchmark

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

Paper No: ICONE29-93353

DOI: https://doi.org/10.1115/ICONE29-93353

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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

Yanfei Qiu

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A033, August 8–12, 2022

Paper No: ICONE29-93201

DOI: https://doi.org/10.1115/ICONE29-93201

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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors

Proceedings Papers

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

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

Paper No: ICONE29-90432

DOI: https://doi.org/10.1115/ICONE29-90432

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Topics: Brayton cycle, Compression, Fast neutron reactors, Supercritical carbon dioxide, Thermal energy

Proceedings Papers

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

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

Paper No: ICONE28-64532

DOI: https://doi.org/10.1115/ICONE28-64532

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Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design

Proceedings Papers

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

Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng

Paper No: ICONE28-63220

DOI: https://doi.org/10.1115/ICONE28-63220

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Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants

Proceedings Papers

Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming

Junyi Li, Zhe Dong, Bowen Li

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A030, August 4–6, 2021

Paper No: ICONE28-64344

DOI: https://doi.org/10.1115/ICONE28-64344

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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

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

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

Paper No: ICONE2020-16368

DOI: https://doi.org/10.1115/ICONE2020-16368

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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

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

Paper No: ICONE2020-16671

DOI: https://doi.org/10.1115/ICONE2020-16671

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Topics: Central heating, Diesel, Fossil fuels, Fuels, Heat, Heating, Plastics, Pyrolysis, Stress, Thermal energy

Proceedings Papers

Validation of Film Evaporation Model in GASFLOW-MPI

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

Paper No: ICONE26-81249

DOI: https://doi.org/10.1115/ICONE26-81249

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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

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

Paper No: ICONE26-81311

DOI: https://doi.org/10.1115/ICONE26-81311

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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

Design and Feasibility Analysis of the Electricity Generation System Based on Residual Heat

Zhe Dong, Miao Liu, Yifei Pan

Paper No: ICONE26-82558

DOI: https://doi.org/10.1115/ICONE26-82558

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Topics: Design, Electric power generation, Heat, Cooling, Generators, Instrumentation, Air flow, Density, Dynamics (Mechanics), Electromagnetic induction

Proceedings Papers

Neutronic Study on a New Concept of Accelerator Driven Subcritical System in China

Jinyang Li, Long Gu, Cunfeng Yao, Dawei Wang, Tianji Peng, Yanlei Zhu

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A007, July 22–26, 2018

Paper No: ICONE26-81329

DOI: https://doi.org/10.1115/ICONE26-81329

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Topics: China, Cycles, Design, Doppler effect, Flow (Dynamics), Gravity (Force), Heavy metals, Neutron sources, Neutrons, Physics

Proceedings Papers

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

A. Zvorykin, M. Mahdi, R. Popov, K. Barati Far, I. Pioro

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A038, July 22–26, 2018

Paper No: ICONE26-81608

DOI: https://doi.org/10.1115/ICONE26-81608

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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

Proceedings Papers

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

Meng Lu, Heng Xie

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A036, July 22–26, 2018

Paper No: ICONE26-81416

DOI: https://doi.org/10.1115/ICONE26-81416

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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

Katarzyna Skolik, Anuj Trivedi, Marina Perez-Ferragut, Chris Allison

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A010, July 22–26, 2018

Paper No: ICONE26-81861

DOI: https://doi.org/10.1115/ICONE26-81861

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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

Zhaoyang Xia, Zhiwei Zhou, Tianji Peng

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A048, July 22–26, 2018

Paper No: ICONE26-82268

DOI: https://doi.org/10.1115/ICONE26-82268

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Topics: Heating, Heat transfer, Critical heat flux, Heat, Superheating, Boilers, Density, Energy generation, Fluid dynamics, Oscillations

Proceedings Papers

A Research Reactor Core Design for Advance Neutron Source

Zeyun Wu

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A059, July 2–6, 2017

Paper No: ICONE25-67573

DOI: https://doi.org/10.1115/ICONE25-67573

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Topics: Design, Neutron sources, Heat flux, Brightness (Photometry), Cycles, Fuels, Neutrons, Thermal energy

Proceedings Papers

Small Modular Pressurized Water Reactors Combined With Conventional Thermal Power Plant

Huijing Jiang, Ning Bai, Huanfen Zhan, Feng Shen, Bin Gao, Xuee Wang

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A010, July 2–6, 2017

Paper No: ICONE25-66690

DOI: https://doi.org/10.1115/ICONE25-66690

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Topics: Pressurized water reactors, Thermal power stations, Hybrid power systems, Steam, Superheating, Boilers, Nuclear power, Carbon, Coal, Emissions

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NARROW

Nuclear Cognition and Public Acceptance

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

Validation of TULIP via ICSBEP Critical Benchmark

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

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

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

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

Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming

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

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

Validation of Film Evaporation Model in GASFLOW-MPI

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

Design and Feasibility Analysis of the Electricity Generation System Based on Residual Heat

Neutronic Study on a New Concept of Accelerator Driven Subcritical System in China

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

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

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

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

A Research Reactor Core Design for Advance Neutron Source

Small Modular Pressurized Water Reactors Combined With Conventional Thermal Power Plant

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