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Proceedings Papers

Improvement of the Thermal-Hydraulic Feedback Model in Bamboo-Core From Single-Channel to Sub-Channel

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Hengrui Zhang, Yunzhao Li, Sicheng Wang, Yisong Li, Yiling Liang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A048, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135973
https://doi.org/10.1115/ICONE31-135973
View Paper titled, Improvement of the Thermal-Hydraulic Feedback Model in Bamboo-Core From Single-Channel to Sub-Channel
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Topics: Feedback, Flow (Dynamics)
Proceedings Papers

Validation of Doppler Reactivity Feedback in SPERT-III E-Core With the Best-Estimate Transient Code TRAC Toshiba Version

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Tohru Egawa, Mikio Tokashiki, Takamasa Miyaji, Takanori Fukunaga
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134116
https://doi.org/10.1115/ICONE31-134116
View Paper titled, Validation of Doppler Reactivity Feedback in SPERT-III E-Core With the Best-Estimate Transient Code TRAC Toshiba Version
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Topics: Accidents, Feedback, Transients (Dynamics)
Proceedings Papers

Reactivity Feedback Effects of Fuel and Grid Plate Expansion in Small Gas-Cooled Fast Reactors

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Yugao Ma, Suyi Zhang, Jian Deng, Jinyu Wang, Yue Liu, Shuhua Ding, Muhao Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A028, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134125
https://doi.org/10.1115/ICONE31-134125
View Paper titled, Reactivity Feedback Effects of Fuel and Grid Plate Expansion in Small Gas-Cooled Fast Reactors
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Topics: Fast neutron reactors, Feedback, Fuels
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

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

Study on Nuclear Safety Management Based on Multiple Nuclear Power Plants Experience Feedback Management

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Shuang Zhang, Sun Xiaoyan
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A053, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93104
https://doi.org/10.1115/ICONE29-93104
View Paper titled, Study on Nuclear Safety Management Based on Multiple Nuclear Power Plants Experience Feedback Management
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Topics: Feedback, Nuclear power stations, Safety
Proceedings Papers

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

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Xiao Ke
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90343
https://doi.org/10.1115/ICONE29-90343
View Paper titled, The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident
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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback
Proceedings Papers

Implementation and Analysis of Thermal Hydraulics Feedback in High-Fidelity Neutron Transport Program HNET

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Yanling Zhu, Chen Hao, Peijun Li, Xiaoyu Zhou
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92724
https://doi.org/10.1115/ICONE29-92724
View Paper titled, Implementation and Analysis of Thermal Hydraulics Feedback in High-Fidelity Neutron Transport Program HNET
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Topics: Feedback, Neutrons, Thermal hydraulics
Proceedings Papers

Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models

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Jesse Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94476
https://doi.org/10.1115/ICONE29-94476
View Paper titled, Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models
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Topics: Boron, Feedback, Physics, Fuels, Linkages, Pressurized water reactors, Boiling, Boron compounds, Corrosion, Cycles
Proceedings Papers

Experience Feedback Report on Hydrogen Meter Discontinuity of Steam Generator Overflow Tube

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Zhang Liu-Huan, Wu Xiang, Ouyang Dong-Fang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90517
https://doi.org/10.1115/ICONE29-90517
View Paper titled, Experience Feedback Report on Hydrogen Meter Discontinuity of Steam Generator Overflow Tube
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Topics: Boilers, Feedback, Hydrogen
Proceedings Papers

Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

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Hua Zheng, Shuhong Wei
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92239
https://doi.org/10.1115/ICONE29-92239
View Paper titled, Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention
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Topics: Design, Feedback, Vessels, Nuclear power stations, Safety, Accident management, Accidents, Construction, Control panels, Control rooms
Proceedings Papers

Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

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Zhang Xingzhen, Sun Hui, Zhao Yanjun, Shi Xianzuo
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92834
https://doi.org/10.1115/ICONE29-92834
View Paper titled, Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant
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Topics: Excitation, Excitation systems, Nuclear power stations, Simulation, Bridges (Structures), Maintenance, Failure, Nuclear power, Accidents, Construction
Proceedings Papers

Strategies and Applications of Big Data and AI Technologies in Nuclear Power Public Opinion Prevention and Control System

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Yun Liang, Shaolin Zhang, Shangyuan Liu
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93779
https://doi.org/10.1115/ICONE29-93779
View Paper titled, Strategies and Applications of Big Data and AI Technologies in Nuclear Power Public Opinion Prevention and Control System
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Topics: Control systems, Nuclear power, Carbon, Carbon neutrality, Simulation, China, Climate change, Construction, Emissions, Feedback
Proceedings Papers

Propulsion Control of Marine Nuclear Reactor by Hardware-in-the-Loop Simulation (HILS)

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Ao Zhang, Xiang Wang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A046, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91544
https://doi.org/10.1115/ICONE29-91544
View Paper titled, Propulsion Control of Marine Nuclear Reactor by Hardware-in-the-Loop Simulation (HILS)
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Topics: Hardware, Nuclear power, Nuclear reactors, Propulsion, Simulation, Feedback, Computer software, Simulation models, Steady state, Transients (Dynamics)
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

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

Experimental Study on Performance Improvement of HTR-10 Helium Purification System

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Fangfang Wang, Liqiang Wei, Tianyu Kang, Chuangguo Hu, Feng Xie, Xiaoming Chen, Lei Shi
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, V001T01A006, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64681
https://doi.org/10.1115/ICONE28-64681
View Paper titled, Experimental Study on Performance Improvement of HTR-10 Helium Purification System
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Topics: Copper, Helium, Particulate matter, Circuits, Desorption, Electron microscopes, Feedback, Flow (Dynamics), High temperature, Service life (Equipment)
Proceedings Papers

Experimental Simulation of Transitions Between Forced Circulation and Natural Circulation With Nuclear Reactivity Feedback

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Hanying Chen, Linzhong Xia, Puzhen Gao, Sichao Tan, Hongsheng Yuan
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, V001T02A034, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66338
https://doi.org/10.1115/ICONE28-66338
View Paper titled, Experimental Simulation of Transitions Between Forced Circulation and Natural Circulation With Nuclear Reactivity Feedback
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Topics: Feedback, Simulation
Proceedings Papers

Influence of Fuel Pellets’ Thermal Expansion on Temperature Feedback Regulation for Megawatt-Class Space Gas-Cooled Fast Reactor

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Yuhao He, Dongdong Yuan, Kewei Ning, Xiaoyu Wang, Fulong Zhao, Sichao Tan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A071, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65504
https://doi.org/10.1115/ICONE28-65504
View Paper titled, Influence of Fuel Pellets’ Thermal Expansion on Temperature Feedback Regulation for Megawatt-Class Space Gas-Cooled Fast Reactor
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Topics: Fast neutron reactors, Feedback, Fuels, Nuclear reactors, Temperature, Thermal expansion, Thermal stresses
Proceedings Papers

Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

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Kazuo Yoshimura, Norihiro Doda, Masaaki Tanaka, Hidemasa Yamano, Kennichi Igawa
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62354
https://doi.org/10.1115/ICONE28-62354
View Paper titled, Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
Open the PDF for Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors in another window
Topics: Dynamics (Mechanics), Evaluation methods, Feedback, Heat sinks, Sodium fast reactors