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Proceedings Papers

Research on Smart Nuclear Power Construction Based on Digitalization and System Engineering in TNPS

Qiang Yang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A007, August 8–12, 2022

Paper No: ICONE29-91570

DOI: https://doi.org/10.1115/ICONE29-91570

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Topics: Nuclear construction, Systems engineering, Construction, Design, Testing, Nuclear power, Decision making, Dimensions, Nuclear power stations, Power stations

Proceedings Papers

Research on Structural Optimization Technology of Fuel Assembly Parts Based on Topology and Optimal Design

Huabin Fan, Shiyin Xu, Huili Jia

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A041, August 8–12, 2022

Paper No: ICONE29-93368

DOI: https://doi.org/10.1115/ICONE29-93368

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Topics: Design, Fuels, Manufacturing, Structural optimization, Topology, Nozzles, Pressure drop, Stress, Coolants, Flow (Dynamics)

Proceedings Papers

Assumption of the Framework for the Evaluation of the Actual Effectiveness of Nuclear Safety Public Communication

Lili Yang, Dan Xing, Yanfei Yang, Meng Chang, Yu Gong

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A006, August 8–12, 2022

Paper No: ICONE29-91382

DOI: https://doi.org/10.1115/ICONE29-91382

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Topics: Safety, Dimensions, Governments, Nuclear industry

Proceedings Papers

PSA Application in UK HPR1000 Numerical Targets Evaluation

Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A038, August 8–12, 2022

Paper No: ICONE29-92462

DOI: https://doi.org/10.1115/ICONE29-92462

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Topics: Damage, Design, Dimensions, Floods, Nuclear power stations, Plant design, Radiation (Physics), Reactor vessels, Risk, Safety

Proceedings Papers

Research on Measurement Method of a Device for Measuring the Perpendicularity of Tubesheet Hole

Xianghua Xu, Guihong Hu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A046, August 8–12, 2022

Paper No: ICONE29-93045

DOI: https://doi.org/10.1115/ICONE29-93045

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Topics: Accuracy and precision, Boilers, Bridges (Structures), Dimensions, Errors, Heat, Inspection, Manufacturing, Surface roughness

Proceedings Papers

100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

Charles Forsberg

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, V001T02A027, August 4–6, 2021

Paper No: ICONE28-64632

DOI: https://doi.org/10.1115/ICONE28-64632

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Topics: Heat, Heat storage, Rocks, Stress, Storage, Fluids, Heat transfer, Plasma spraying, Spraying (Coating processes), Dimensions

Proceedings Papers

Deposition Velocity and Penetration Efficiency in a Square Channel Using a Lagrangian-Based Modeling Approach

Byung-Hee Choi, Daniel Orea, Thien Nguyen, N. K. Anand, Yassin Hassan, Piyush Sabharwall

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, V001T03A026, August 4–5, 2020

Paper No: ICONE2020-16907

DOI: https://doi.org/10.1115/ICONE2020-16907

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Topics: Computational fluid dynamics, Computer simulation, Dimensions, Drag (Fluid dynamics), Ducts, Fast neutron reactors, Flow (Dynamics), Modeling, Particulate matter, Reynolds number

Proceedings Papers

Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire

Gota Suga, Tetsuaki Takeda

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A040, August 4–5, 2020

Paper No: ICONE2020-16705

DOI: https://doi.org/10.1115/ICONE2020-16705

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Topics: Fluid dynamics, Heat transfer, Wire, Very high temperature reactors, Flow (Dynamics), Natural convection, Cooling, Cooling systems, Copper, Gas turbines

Proceedings Papers

Development of a Simplified Model for Aerosol Removal by Spray System of Containment

Yu Huiyu, Gu Haifeng, Chen Junyan, Sun Zhongning

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A024, August 4–5, 2020

Paper No: ICONE2020-16353

DOI: https://doi.org/10.1115/ICONE2020-16353

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Topics: Aerosols, Containment, Sprays, Drops, Accidents, Air flow, Dimensions, Gas flow, Instrumentation, Momentum

Proceedings Papers

Uranium Enrichment Measurement Using Enrichment-Meter Approach

K. Abd El Gawad, Yushou Song

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A039, July 22–26, 2018

Paper No: ICONE26-82101

DOI: https://doi.org/10.1115/ICONE26-82101

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Topics: Uranium, Containers, Simulation, Accuracy and precision, Wall thickness, Calibration, Dimensions, Equilibrium (Physics), Gamma ray spectrometry, Germanium

Proceedings Papers

A Neutronics Feasibility Study of the TRIGA LEU Fuel in the 20MWt NIST Research Reactor

Kyle Anthony Britton, Zeyun Wu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A088, July 22–26, 2018

Paper No: ICONE26-82433

DOI: https://doi.org/10.1115/ICONE26-82433

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Topics: Fuels, National Institute of Standards and Technology, Uranium, Density, Dimensions, Fuel rods, Performance characterization, Sustainability

Proceedings Papers

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

Christopher Bennett, Scott Adams, Nick Alexander

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A021, July 22–26, 2018

Paper No: ICONE26-82628

DOI: https://doi.org/10.1115/ICONE26-82628

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Topics: Architects, Boilers, Databases, Design, Dimensions, Engineering disciplines, Nuclear power stations, Nuclear reactors, Safety, Small modular reactors

Proceedings Papers

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong

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, V001T13A002, July 22–26, 2018

Paper No: ICONE26-81159

DOI: https://doi.org/10.1115/ICONE26-81159

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Topics: Nuclear power stations, Ocean engineering, Seawater, Boilers, Design, Dimensions, Hazards, Heat, Accidents, Computers

Proceedings Papers

Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator

Meng-Ran Liao, Chun-Hui Dai, Can Ma, Yong Liu, Zheng-Xing Zhao, Zhou-Yang Liu

Paper No: ICONE26-82231

DOI: https://doi.org/10.1115/ICONE26-82231

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Topics: Generators, Liquid metals, Magnetohydrodynamics, Two-phase flow, Fluids, Porosity, Temperature, Bubbles, Cycles, Dimensions

Proceedings Papers

Structural Analysis and Manufacturing of HL-2M Vacuum Vessel and Support Structures

Yuncong Huang, Hong Ran, Zeng Cao, Jilai Hou, Binbin Song

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A006, July 22–26, 2018

Paper No: ICONE26-81273

DOI: https://doi.org/10.1115/ICONE26-81273

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Topics: Manufacturing, Structural analysis, Vacuum, Vessels, Stress, Tokamaks, Construction, Plasmas (Ionized gases), Rods, Dimensions

Proceedings Papers

Heat Transfer and Fluid Flow Characteristics of One Side Heated Vertical Rectangular Channel Applied As Vessel Cooling System of VHTR

Kenta Fujikami, Tetsuaki Takeda, Shumpei Funatani

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A046, July 22–26, 2018

Paper No: ICONE26-81700

DOI: https://doi.org/10.1115/ICONE26-81700

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Topics: Cooling systems, Fluid dynamics, Heat transfer, Very high temperature reactors, Vessels, Flow (Dynamics), Natural convection, Porosity, Porous materials, Cooling

Proceedings Papers

Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices

Qian Zhang, Qiang Zhao, Hongchun Wu, Liangzhi Cao, Zheng Zheng

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A002, July 22–26, 2018

Paper No: ICONE26-81041

DOI: https://doi.org/10.1115/ICONE26-81041

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Topics: Resonance, Fuels, Density, Dimensions, Pins (Engineering)

Proceedings Papers

Analysis of the Thermal-Hydraulic and Mechanical Performance of Intermediate Heat Exchangers Used in Systems With Very High Temperature Nuclear Reactors

Raciel de la Torre Valdés, Juan Luis Francois Lacouture

Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T04A004, June 24–28, 2018

Paper No: NUCLRF2018-7620

DOI: https://doi.org/10.1115/NUCLRF2018-7620

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Topics: Equipment performance, Heat exchangers, High temperature, Nuclear reactors, Computational fluid dynamics, Design, Stress, Circuits, Compacting, Dimensions

Proceedings Papers

Analysis on Radioactive Gas Movement and Delay Status Before Release

Bo Nan Zhu

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A017, July 2–6, 2017

Paper No: ICONE25-66713

DOI: https://doi.org/10.1115/ICONE25-66713

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Topics: Delays, Activated carbon, Design, Dimensions, Flow (Dynamics), Computational methods, Design methodology, Isotopes, Nuclear fission, Nuclear power stations

Proceedings Papers

Researches on the Test of Web Local Failure Modes and Related FEA Study

Wenyu Xiao, Bingbing Liang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A091, July 2–6, 2017

Paper No: ICONE25-67261

DOI: https://doi.org/10.1115/ICONE25-67261

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Topics: Failure mechanisms, Finite element analysis, Design, Steel, Buckling, China, Dimensions, Compression, Evaluation methods, Failure

NARROW

Research on Smart Nuclear Power Construction Based on Digitalization and System Engineering in TNPS

Research on Structural Optimization Technology of Fuel Assembly Parts Based on Topology and Optimal Design

Assumption of the Framework for the Evaluation of the Actual Effectiveness of Nuclear Safety Public Communication

PSA Application in UK HPR1000 Numerical Targets Evaluation

Research on Measurement Method of a Device for Measuring the Perpendicularity of Tubesheet Hole

100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

Deposition Velocity and Penetration Efficiency in a Square Channel Using a Lagrangian-Based Modeling Approach

Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire

Development of a Simplified Model for Aerosol Removal by Spray System of Containment

Uranium Enrichment Measurement Using Enrichment-Meter Approach

A Neutronics Feasibility Study of the TRIGA LEU Fuel in the 20MWt NIST Research Reactor

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator

Structural Analysis and Manufacturing of HL-2M Vacuum Vessel and Support Structures

Heat Transfer and Fluid Flow Characteristics of One Side Heated Vertical Rectangular Channel Applied As Vessel Cooling System of VHTR

Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices

Analysis of the Thermal-Hydraulic and Mechanical Performance of Intermediate Heat Exchangers Used in Systems With Very High Temperature Nuclear Reactors

Analysis on Radioactive Gas Movement and Delay Status Before Release

Researches on the Test of Web Local Failure Modes and Related FEA Study

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