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Proceedings Papers

Development of Requirements for Demonstrating Structural Integrity of the Highest Reliability Components

Antony Hurst, Louis Chang, Mike Nielsen, Sam Holcroft
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136097
https://doi.org/10.1115/ICONE31-136097
View Paper titled, Development of Requirements for Demonstrating Structural Integrity of the Highest Reliability Components
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Topics: Design, Reliability, Safety, Failure, Nuclear power, Jets, Missiles, Pressure, Classification, Construction
Proceedings Papers

AHPR1000: Simplified, Intelligent and Environment-Friendly Advanced Nuclear Power Plant

Yuxiang Wu, Qianwen Liu, Di Yao, Guangfei Wang, Simin Xu, Yang Lu, Chengcheng Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135079
https://doi.org/10.1115/ICONE31-135079
View Paper titled, AHPR1000: Simplified, Intelligent and Environment-Friendly Advanced Nuclear Power Plant
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Topics: Nuclear power stations, Safety, Design, Maintenance, Accidents, Aircraft, Carbon, Chain, China, Construction
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

Experimental Investigation on the Heat Transfer Capacity of a Prototypically Long Straight Thermosyphon Bundle for Nuclear Spent Fuel Pool Passive Cooling

Sergio Iván Cáceres Castro, Rudi Kulenovic, Jörg Starflinger
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A031, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136234
https://doi.org/10.1115/ICONE31-136234
View Paper titled, Experimental Investigation on the Heat Transfer Capacity of a Prototypically Long Straight Thermosyphon Bundle for Nuclear Spent Fuel Pool Passive Cooling
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Topics: Cooling, Heat transfer, Safety, Spent nuclear fuels
Proceedings Papers

Experimental Study in Cooling Rate by Containment Spay

Ning Wang, Yapeng Yang, Zhe Liu
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135031
https://doi.org/10.1115/ICONE31-135031
View Paper titled, Experimental Study in Cooling Rate by Containment Spay
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Topics: Containment, Cooling
Proceedings Papers

Design and Evaluation of Mitigation Measures for Tsinghua High Flux Reactor Loss-of-Coolant Accidents

Zhuang Wang, Heng Xie, Gan Zhu, Szu-En Yeh
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134999
https://doi.org/10.1115/ICONE31-134999
View Paper titled, Design and Evaluation of Mitigation Measures for Tsinghua High Flux Reactor Loss-of-Coolant Accidents
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Topics: Cooling, Design, Emergencies, Loss of coolant accidents
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

OpenFOAM-Based Benchmarking Simulations of Xe Gas Behavior in Molten Lead for Advanced Fast Reactors

Emir Hanic, Xiang Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A071, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135256
https://doi.org/10.1115/ICONE31-135256
View Paper titled, OpenFOAM-Based Benchmarking Simulations of Xe Gas Behavior in Molten Lead for Advanced Fast Reactors
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Topics: Fast neutron reactors, Simulation, Alpha decay, Bubbles, Computational fluid dynamics, Computer simulation, Computer software, Cooling, Fluids, Multiphase flow
Proceedings Papers

Design and Performance Verification of Passive Core Cooling System Strainer in Advanced Nuclear Power Plants of China

Ruolin Huang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A051, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134892
https://doi.org/10.1115/ICONE31-134892
View Paper titled, Design and Performance Verification of Passive Core Cooling System Strainer in Advanced Nuclear Power Plants of China
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Topics: China, Cooling, Cooling systems, Design, Emergency core cooling systems, Nuclear power stations, Loss of coolant accidents, Filters, Aluminum, Coating processes
Proceedings Papers

Effect of Geometric Parameters on Cooling Performance of The Concrete Shielding for Swimming Pool-Type Low-Temperature Heating Reactor

Guangming Fan, Shuai Hao, Zongkun Li, Jiaming Li, Shicong Guan
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134626
https://doi.org/10.1115/ICONE31-134626
View Paper titled, Effect of Geometric Parameters on Cooling Performance of The Concrete Shielding for Swimming Pool-Type Low-Temperature Heating Reactor
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Topics: Concretes, Cooling, Heating, Low temperature
Proceedings Papers

Droplet Evaporation Characteristics on High-Temperature Porous Surfaces for Cooling Fuel Debris

Kohei Yuki, Naoki Horiguchi, Hiroyuki Yoshida, Kazuhisa Yuki
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A072, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135281
https://doi.org/10.1115/ICONE31-135281
View Paper titled, Droplet Evaporation Characteristics on High-Temperature Porous Surfaces for Cooling Fuel Debris
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Topics: Cooling, Drops, Evaporation, Fuels, High temperature, Porous materials
Proceedings Papers

Study on the Improvement of RELAP5 Post-Critical Boiling Heat Transfer Model for the Submerged Cooling Process of Rectangular Channel

Lei Zhong, Hongxing Yu, Chen Ling, Deqi Chen, Jian Deng, Haidong Liu, Jun Xu
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131657
https://doi.org/10.1115/ICONE31-131657
View Paper titled, Study on the Improvement of RELAP5 Post-Critical Boiling Heat Transfer Model for the Submerged Cooling Process of Rectangular Channel
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Topics: Boiling, Cooling, Heat transfer
Proceedings Papers

Experimental Study on Startup and Heat Transfer Performance of High Temperature Sodium Heat Pipe

Shunli Jiang, Huihui Zhou, Youjia Zhang, Dewen Yuan, Shanfang Huang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A069, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135210
https://doi.org/10.1115/ICONE31-135210
View Paper titled, Experimental Study on Startup and Heat Transfer Performance of High Temperature Sodium Heat Pipe
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Topics: Cooling, Heat pipes, Heat transfer, Heating, High temperature, Sodium
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
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Topics: Chain, Computer simulation, Coolants, Cooling, Heat transfer, Resolution (Optics), Sensitivity analysis, Shapes, Slug flows, Water
Proceedings Papers

Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000

Zhengrun Shang, Dufeng Lv, Zhaoming Meng, Zhongning Sun
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135645
https://doi.org/10.1115/ICONE31-135645
View Paper titled, Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000
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Topics: Accidents, Containment, Cooling, Cooling systems, Design, Loss of coolant accidents, Nuclear reactor coolants, Pipelines, Pressure, Redundancy (Engineering)
Proceedings Papers

Experimental Investigation on the Survival of Cooling Tube in Molten Pool

Jie Pei, Fengyang Quan, Wei Li, Yidan Yuan
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134398
https://doi.org/10.1115/ICONE31-134398
View Paper titled, Experimental Investigation on the Survival of Cooling Tube in Molten Pool
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Topics: Cooling
Proceedings Papers

Remote Measurement by Robot Arm Equipped With PAUVP and LIBS

Chengzuo Ji, Yuan Chen, Christian Brice, Hiroshige Kikura, Hideharu Takahashi, Gen Endo
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A063, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135489
https://doi.org/10.1115/ICONE31-135489
View Paper titled, Remote Measurement by Robot Arm Equipped With PAUVP and LIBS
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Topics: Flow (Dynamics), Robots, Leakage, Sediments, Water, Nuclear power stations, Fuels, Fukushima nuclear disaster, Japan, 2011, Nuclear decommissioning, Accidents
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)
Proceedings Papers

Investigation of Compressible Flow in Natural Circulation Loops With a Non-Boussinesq Algorithm

Jinsong Zhang, Yongyong Wu, Nan Gui, Zhen Zhang, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A029, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134557
https://doi.org/10.1115/ICONE31-134557
View Paper titled, Investigation of Compressible Flow in Natural Circulation Loops With a Non-Boussinesq Algorithm
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Topics: Algorithms, Compressible flow, Lattice Boltzmann methods, Flow (Dynamics), Temperature, Density, Heat transfer, Nuclear reactors, Pressure, Reliability
Proceedings Papers

Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils

Jiaqi Wang, Yanfeng Xie, Xiaolong Liu, Jianpeng Meng, Ruibao Jia, Qiang Li, Xin Chen
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92917
https://doi.org/10.1115/ICONE29-92917
View Paper titled, Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils
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Topics: Cooling, Water