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Proceedings Papers

Research on a Space Reactor Scheme for the Lunar Research Station

Zhipeng Wang, Qiang Sheng, Zijing Liu, Ke Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-125424
https://doi.org/10.1115/ICONE31-125424
View Paper titled, Research on a Space Reactor Scheme for the Lunar Research Station
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Topics: Cycles, Design, Energy / power systems, Energy generation, Flow (Dynamics), Fuel rods, Heat transfer, Magnetohydrodynamics, Modeling, NASA
Proceedings Papers

Evaluation and Sensitivity Study of Uniform Kernel Method in Atmospheric 41 Ar Dispersion Against the Belgian Field Experiment

Yeshuai Sun, Yujie Zhang, Zhaoyang Wang, Li Yang, Xinpeng Li, Yixue Chen, Xinwen Dong, Sheng Fang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A022, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135061
https://doi.org/10.1115/ICONE31-135061
View Paper titled, Evaluation and Sensitivity Study of Uniform Kernel Method in Atmospheric 41 Ar Dispersion Against the Belgian Field Experiment
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Topics: Contamination, Databases, Density, Emergency response, Engineering simulation, Meteorology, Nuclear power stations, Particulate matter, Radioisotopes, Sensitivity analysis
Proceedings Papers

Model Evaluation and Parallelization of Subchannel Analysis Code for Full-Core Pin-by-Pin Analysis

Zhonghao Yu, Jinbiao Xiong
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133784
https://doi.org/10.1115/ICONE31-133784
View Paper titled, Model Evaluation and Parallelization of Subchannel Analysis Code for Full-Core Pin-by-Pin Analysis
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Topics: Databases, Errors, Flow (Dynamics), Friction, Modeling, Nuclear power plant operations, Nuclear reactors, Optimization, Pressurized water reactors, Resolution (Optics)
Proceedings Papers

Application of Sensitivity Analysis Techniques to a Low Dimensional Problem in the Frame of Severe Accidents

Michela Angelucci, Sandro Paci, Salvatore Angelo Cancemi, Rosa Lo Frano
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A087, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135801
https://doi.org/10.1115/ICONE31-135801
View Paper titled, Application of Sensitivity Analysis Techniques to a Low Dimensional Problem in the Frame of Severe Accidents
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Topics: Accidents, Sensitivity analysis
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

Uncertainty and Sensitivity Analysis of Phebus FPT-1 Experiment Based on Severe Accident Analysis Code ISAA

Hao Yang, Bin Zhang, Jishen Li, Pengcheng Gao, Zhiran Zhang, Fan Miao
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A078, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136230
https://doi.org/10.1115/ICONE31-136230
View Paper titled, Uncertainty and Sensitivity Analysis of Phebus FPT-1 Experiment Based on Severe Accident Analysis Code ISAA
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Topics: Accidents, Sensitivity analysis, Uncertainty, Uncertainty analysis
Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis
Proceedings Papers

Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR

Yuxuan Liang, Xiang Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A068, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92887
https://doi.org/10.1115/ICONE29-92887
View Paper titled, Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR
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Topics: Accidents, Fuels, Sensitivity analysis, Uncertainty analysis
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93244
https://doi.org/10.1115/ICONE29-93244
View Paper titled, Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model
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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)
Proceedings Papers

Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor

Ang Li, Yuqing Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90347
https://doi.org/10.1115/ICONE29-90347
View Paper titled, Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor
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Topics: Accidents, Flow (Dynamics), Pressurized water reactors, Sensitivity analysis, Uncertainty
Proceedings Papers

A Sensitivity Analysis of Condensation Phenomena for a Passive Containment Cooling System by Using Code_Saturne Coupled With OpenTURNS

Ru Chen, Ronghao Liang, Lu Zhou, Jiesheng Min
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92164
https://doi.org/10.1115/ICONE29-92164
View Paper titled, A Sensitivity Analysis of Condensation Phenomena for a Passive Containment Cooling System by Using Code_Saturne Coupled With OpenTURNS
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Topics: Condensation, Containment, Cooling systems, Metamodeling, Sensitivity analysis
Proceedings Papers

Simulation of MSLB+SBO Nuclear Accident Drill Sequence of 3rd-Generation Passive Nuclear Power Plant Based on Severe Accident Simulator

Yongyong Yang, Xiong Huang, Wei Wei, Yinyong Tao, Zhengquan Xie, Guoyang Ma
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90732
https://doi.org/10.1115/ICONE29-90732
View Paper titled, Simulation of MSLB+SBO Nuclear Accident Drill Sequence of 3rd-Generation Passive Nuclear Power Plant Based on Severe Accident Simulator
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Topics: Accidents, Drills (Tools), Emergencies, Nuclear power stations, Sensitivity analysis, Simulation
Proceedings Papers

Sensitivity Analysis on Key Parameters of Severe Accident Source Term of PWR

Pingwen Ou, Yongzheng Chen, Dongyu He, Peng Chen
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91730
https://doi.org/10.1115/ICONE29-91730
View Paper titled, Sensitivity Analysis on Key Parameters of Severe Accident Source Term of PWR
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Topics: Accidents, Pressurized water reactors, Sensitivity analysis
Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93417
https://doi.org/10.1115/ICONE29-93417
View Paper titled, Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature
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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis
Proceedings Papers

Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State

Yanzhu Chen, Zhi Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91782
https://doi.org/10.1115/ICONE29-91782
View Paper titled, Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State
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Topics: Nuclear power stations, Probability, Safety, Risk, Maintenance, Damage, Heat, Power grids, Power stations, Sensitivity analysis
Proceedings Papers

Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor

Yanzhu Chen, Zhichao Yang
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, V003T13A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65152
https://doi.org/10.1115/ICONE28-65152
View Paper titled, Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor
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Topics: Fire, Ignition, Probability, Safety, Design, Evaluation methods, Innovation, Sensitivity analysis
Proceedings Papers

Sensitivity Analysis on the Blast Resistance of Steel Concrete Structure Wall Based on CONWEP

Guopeng Ren, Rong Pan, Feng Sun, Liang Li
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, V003T12A022, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64415
https://doi.org/10.1115/ICONE28-64415
View Paper titled, Sensitivity Analysis on the Blast Resistance of Steel Concrete Structure Wall Based on CONWEP
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Topics: Concretes, Sensitivity analysis, Steel
Proceedings Papers

Hydrodynamic Analysis of Steam Generator Under LOCA Conditions

Xiaoqiang He, Puzhen Gao, Weichao Yuan
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, V003T12A030, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64709
https://doi.org/10.1115/ICONE28-64709
View Paper titled, Hydrodynamic Analysis of Steam Generator Under LOCA Conditions
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Topics: Boilers, Fluid-dynamic forces, Pressure, Accidents, Nuclear power stations, Coolants, Design, Flow (Dynamics), Fluids, Nozzles
Proceedings Papers

Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR

Mingqiang Song, Ningna Zhang, Xiaoming Yang, Rubing Ma, Zhiyi Yang, Chao Ding
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, V003T09A006, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64749
https://doi.org/10.1115/ICONE28-64749
View Paper titled, Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR
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Topics: Accidents, Sensitivity analysis, Hydrogen production, Nuclear industry, China, Coolants, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pressure
Proceedings Papers

Modeling and Sensitivity Analysis of the Sodium-Water Reaction Accident in Parallel Channels

Gang Luo, Peiwei Sun, Xi Bai, Huasong Cao, Kai Wang, Huanjun Zhu
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A048, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64490
https://doi.org/10.1115/ICONE28-64490
View Paper titled, Modeling and Sensitivity Analysis of the Sodium-Water Reaction Accident in Parallel Channels
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Topics: Accidents, Modeling, Pressure, Sensitivity analysis, Sodium, Sodium fast reactors, Water, Wave propagation