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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

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

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

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
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, V001T13A018, July 22–26, 2018
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

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

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
Proceedings Papers

Thermal Stratification Analysis and Fatigue Evaluation for Pressurizer Surge Line in Nuclear Power Plant

Xiao Xu, Pan Liu, Guihe Zhang, Dasheng Wang, Ting Jin
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A082, July 2–6, 2017
Paper No: ICONE25-67118
DOI: https://doi.org/10.1115/ICONE25-67118
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Topics: Fatigue, Nuclear power stations, Surges, Thermal stratification, Stress, Dimensions, Boundary layers, Fluids, Numerical analysis, Temperature
Proceedings Papers

Nuclear Island Basemat Modeling for Generation III Nuclear Power Plant Design in China

Ziduan Shang, Chunhua Wu, Boyu Han, Chenyu Chang, Lutong Zhang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A038, July 2–6, 2017
Paper No: ICONE25-66346
DOI: https://doi.org/10.1115/ICONE25-66346
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Topics: China, Modeling, Nuclear design, Soil, Stress, Design, Concretes, Safety, Containment vessels, Dimensions
Proceedings Papers

Design and Analysis of Key Instruments of Supercritical Carbon Dioxide Brayton Cycle in Future Nuclear Power Field

Lin Yuansheng, Wu Jun, Ma Can, Dai Chunhui, Zhao Zhenxing, Tao Mo
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A084, July 2–6, 2017
Paper No: ICONE25-67155
DOI: https://doi.org/10.1115/ICONE25-67155
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Topics: Brayton cycle, Design, Instrumentation, Nuclear power, Supercritical carbon dioxide, Compressors, Turbines, Impellers, Thermodynamic power cycles, Flow (Dynamics)
Proceedings Papers

A New Numerical Method for Fuel Temperature Calculation

Jin Xin, Xiaohan Liu, Xiaoyan Wei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A009, July 2–6, 2017
Paper No: ICONE25-66248
DOI: https://doi.org/10.1115/ICONE25-66248
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Topics: Fuels, Numerical analysis, Temperature, Heat conduction, Stability, Fuel rods, Thermal conductivity, Density, Dimensions, Specific heat
Proceedings Papers

Application of a 3D Discrete Ordinates-Monte Carlo Coupling Method on CAP1400 Cavity Streaming Calculation

Zheng Zheng, Hui Li, Mengqi Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A011, July 2–6, 2017
Paper No: ICONE25-66401
DOI: https://doi.org/10.1115/ICONE25-66401
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Topics: Cavities, Fluence (Radiation measurement), Neutrons, Photons, Errors, Computation, Dimensions, Geometry, Modeling, Nuclear power stations