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Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022

Paper No: ICONE29-93244

DOI: https://doi.org/10.1115/ICONE29-93244

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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)

Proceedings Papers

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A026, August 8–12, 2022

Paper No: ICONE29-92284

DOI: https://doi.org/10.1115/ICONE29-92284

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Topics: Heat, Molten salt reactors, Numerical analysis

Proceedings Papers

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022

Paper No: ICONE29-91761

DOI: https://doi.org/10.1115/ICONE29-91761

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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat

Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022

Paper No: ICONE29-92103

DOI: https://doi.org/10.1115/ICONE29-92103

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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results

Proceedings Papers

Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor

Jun Zhang, Daogang Lu, Jinsong Guo, Yuhao Zhang, Danting Sui

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A025, August 8–12, 2022

Paper No: ICONE29-92794

DOI: https://doi.org/10.1115/ICONE29-92794

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Topics: Fast neutron reactors, Heat, Heat transfer, Sodium

Proceedings Papers

An Optimal Design Method for Passive Residual Heat Removal System

Yuepeng Bi

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A015, August 8–12, 2022

Paper No: ICONE29-92518

DOI: https://doi.org/10.1115/ICONE29-92518

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Topics: Design methodology, Genetic algorithms, Heat

Proceedings Papers

A Modified Two-Zone Model for Predicting Heat Release Rate of Pool Fire in a Confined Space

Lan Peng, Xianjia Huang, Jinkai Wang, He Zhu, Ping Yang, Chaoliang Xing, Chunyang Zhao

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A042, August 8–12, 2022

Paper No: ICONE29-92422

DOI: https://doi.org/10.1115/ICONE29-92422

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Topics: Heat, Liquid pool fires, Oxygen

Proceedings Papers

Research on Heat Transfer Performance of Heat Pipe in Mobile Small Reactor

Huaichang Lu, Tao Zhou, Wenbin Liu, Jianyu Tang, Tianyu Gao

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A024, August 8–12, 2022

Paper No: ICONE29-91655

DOI: https://doi.org/10.1115/ICONE29-91655

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Topics: Heat pipes, Heat transfer, Temperature, Thermal resistance, Computer simulation, Computer software, Heat, Heat transfer coefficients, High temperature, Mechanical admittance

Proceedings Papers

Feasibility Study of Passive Water-Cooled Residual Heat Removal Scheme for Small Reactors

Fei Yu, Yueming Fu, Feng Zhu, Mingqian Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A048, August 8–12, 2022

Paper No: ICONE29-92779

DOI: https://doi.org/10.1115/ICONE29-92779

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Topics: Heat, Safety, Water

Proceedings Papers

Analysis of Thermal Stratification Effects in the Ring Headers of the Passive Residual Heat Removal System of NHR-200-II

Yiwa Geng, Xiongbin Liu

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A024, August 8–12, 2022

Paper No: ICONE29-90285

DOI: https://doi.org/10.1115/ICONE29-90285

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Topics: Computational fluid dynamics, Heat, Thermal stratification

Proceedings Papers

Experiment Investigation on Onset of Flow Instability in Upward Tube Under Low Pressure Condition

Bing Yang, Minfu Zhao, Junhan Wei

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A035, August 8–12, 2022

Paper No: ICONE29-90817

DOI: https://doi.org/10.1115/ICONE29-90817

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Topics: Flow instability, Pressure, Pressure drop, Two-phase flow, Bubbles, Cooling, Flow (Dynamics), Fluids, Heat, Heat flux

Proceedings Papers

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Shotaro Osako, Xin Li, Akifumi Yamaji

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A009, August 8–12, 2022

Paper No: ICONE29-89102

DOI: https://doi.org/10.1115/ICONE29-89102

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Topics: Accidents, Fuels, Fukushima nuclear disaster, Japan, 2011, Heat, Oxidation, Melting, Temperature, Leakage, Nuclear decommissioning, Nuclear power stations

Proceedings Papers

Investigation on Start-Up Characteristics of Secondary Passive Residual Heat Removal System Under Rolling Condition

Ao Sun, Jie Cheng, Dongbao Zhu, Chunping Tian, Pengzheng Li

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A040, August 8–12, 2022

Paper No: ICONE29-91508

DOI: https://doi.org/10.1115/ICONE29-91508

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Topics: Heat, Thermal stratification, Nuclear power stations, Ocean engineering, Boilers, Cooling, Design, Flow (Dynamics), Heat exchangers, Oceans

Proceedings Papers

Experimental Assessment of RELAP5 for the Prediction of Passive Residual Heat Removal Capacity of the Intermediate Heat Exchange Loop

Zhanfei Qi, Yanhua Wu, Zijiang Yang, Yao Xiao, Junlong Li

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A039, August 8–12, 2022

Paper No: ICONE29-91486

DOI: https://doi.org/10.1115/ICONE29-91486

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Topics: Heat

Proceedings Papers

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022

Paper No: ICONE29-89568

DOI: https://doi.org/10.1115/ICONE29-89568

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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability

Proceedings Papers

Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method

Si Junping, Liu Xiaosong, Zhao Wenbin, Xu Yuheng, Lei Jin, Zhang Wenlong, Huang Gang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A031, August 8–12, 2022

Paper No: ICONE29-90468

DOI: https://doi.org/10.1115/ICONE29-90468

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Topics: Fuels, Heat, High temperature, Irradiation (Radiation exposure), Manufacturing, Optimization, Steady state, Thermal analysis, Water

Proceedings Papers

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

Guogang Bao, Changdong Lu, Weiwei Wang, Ren Liang, Zhikang Lin, Yong Ouyang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A013, August 8–12, 2022

Paper No: ICONE29-89383

DOI: https://doi.org/10.1115/ICONE29-89383

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Topics: Accidents, Cladding systems (Building), Coolants, Damage, Fuel rods, Heat, Pressure, Resonance ionization spectroscopy, Safety, Leakage

Proceedings Papers

The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor

Xia Yan, Xuedong Ou, Mingqiang Lin, Jian Mou, Shaolei Sun, Chunyun Chi, Chunqing Zhao, Qin Zhou

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A045, August 8–12, 2022

Paper No: ICONE29-93465

DOI: https://doi.org/10.1115/ICONE29-93465

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Topics: Design, Fuels, Compression, Coolants, Flow (Dynamics), Generators, Gravity (Force), Heat, Heat transfer, Nuclear design

Proceedings Papers

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A020, August 8–12, 2022

Paper No: ICONE29-91669

DOI: https://doi.org/10.1115/ICONE29-91669

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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains

Proceedings Papers

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

Jie Zhang, Jing Wang, Peiying Zhang, Kun Tan, Minxue Yang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A024, August 8–12, 2022

Paper No: ICONE29-91837

DOI: https://doi.org/10.1115/ICONE29-91837

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Topics: China, Construction, Nuclear power stations, Water, Safety, Risk, Accidents, Maintenance, Pressurized water reactors, Cooling

NARROW

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor

An Optimal Design Method for Passive Residual Heat Removal System

A Modified Two-Zone Model for Predicting Heat Release Rate of Pool Fire in a Confined Space

Research on Heat Transfer Performance of Heat Pipe in Mobile Small Reactor

Feasibility Study of Passive Water-Cooled Residual Heat Removal Scheme for Small Reactors

Analysis of Thermal Stratification Effects in the Ring Headers of the Passive Residual Heat Removal System of NHR-200-II

Experiment Investigation on Onset of Flow Instability in Upward Tube Under Low Pressure Condition

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Investigation on Start-Up Characteristics of Secondary Passive Residual Heat Removal System Under Rolling Condition

Experimental Assessment of RELAP5 for the Prediction of Passive Residual Heat Removal Capacity of the Intermediate Heat Exchange Loop

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

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