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Proceedings Papers

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

Da Yan, Kaiyue Shen, Yicheng Guo, Huaqiang Yin, Xuedong He, Tao Ma
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, V001T02A004, August 4–6, 2021
Paper No: ICONE28-63633
DOI: https://doi.org/10.1115/ICONE28-63633
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Topics: Carbon, Dehumidification, Thermogravimetry, Very high temperature reactors, Temperature, Boron, Graphite, High temperature, Corrosion, Desorption
Proceedings Papers

Oxidation Behaviors of the High Temperature Alloys in the Impure Helium and Argon

Wei Zheng, Haoxiang Li, Qiuhao Wang, Huaqiang Yin, Xuedong He, Hua Fan, Tao Ma
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, V001T02A005, August 4–6, 2021
Paper No: ICONE28-63659
DOI: https://doi.org/10.1115/ICONE28-63659
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Topics: Alloys, Corrosion, Helium, High temperature, Oxidation, Very high temperature reactors
Proceedings Papers

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Jinhua Wang, Yuchen Hao, Yue Li, Bin Wu, Haitao Wang, Tao Ma
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, V001T02A002, August 4–6, 2021
Paper No: ICONE28-63134
DOI: https://doi.org/10.1115/ICONE28-63134
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Topics: Fuels, Gas cooled reactors, High temperature, Nuclear power, Transportation systems
Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, 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, V001T04A015, August 4–6, 2021
Paper No: ICONE28-65765
DOI: https://doi.org/10.1115/ICONE28-65765
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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics
Proceedings Papers

UHT Test Facility Updates and Oxidation Tests for Accident Tolerant Fuel Development

William A. Byers, Guoqiang Wang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A042, August 4–6, 2021
Paper No: ICONE28-66592
DOI: https://doi.org/10.1115/ICONE28-66592
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Topics: Accidents, Fuels, High temperature, Oxidation, Test facilities, Zirconium alloys
Proceedings Papers

Experimental Study on Performance Improvement of HTR-10 Helium Purification System

Fangfang Wang, Liqiang Wei, Tianyu Kang, Chuangguo Hu, Feng Xie, Xiaoming Chen, Lei Shi
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, V001T01A006, August 4–6, 2021
Paper No: ICONE28-64681
DOI: https://doi.org/10.1115/ICONE28-64681
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Topics: Copper, Helium, Particulate matter, Circuits, Desorption, Electron microscopes, Feedback, Flow (Dynamics), High temperature, Service life (Equipment)
Proceedings Papers

Corrosion Behavior of Superalloys in High Temperature Gas Cooled Reactor in Impure Helium With Corrosion Time

Haoxiang Li, Bin Du, Wei Zheng, Qiuhao Wang, Huaqiang Yin, Xuedong He, Hua Fan, Tao Ma
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, V001T02A011, August 4–6, 2021
Paper No: ICONE28-64351
DOI: https://doi.org/10.1115/ICONE28-64351
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Topics: Corrosion, Gas cooled reactors, Helium, High temperature, Oxidation, Superalloys
Proceedings Papers

Study on Water Cooler Performance for High Temperature Helium Experimental System

Qingxiang Hu, Wei Peng, Gang Zhao, Jie Wang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A033, August 4–6, 2021
Paper No: ICONE28-65596
DOI: https://doi.org/10.1115/ICONE28-65596
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Topics: Heat exchangers, Helium, High temperature, Very high temperature reactors, Water
Proceedings Papers

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang
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, V001T03A008, August 4–6, 2021
Paper No: ICONE28-65406
DOI: https://doi.org/10.1115/ICONE28-65406
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Topics: Ceramics, Fast neutron reactors, High temperature, Neutrons, Nuclear fuel cycle, Physics, Spent nuclear fuels
Proceedings Papers

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

Charles Forsberg, Daniel Stack, Patrick McDaniel
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, V001T02A028, August 4–6, 2021
Paper No: ICONE28-64638
DOI: https://doi.org/10.1115/ICONE28-64638
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Topics: Combined cycles, Heat storage, Hydrogen, Heat, Compressed air, High temperature, Combined cycle gas turbines, Carbon, Cycles, Energy storage
Proceedings Papers

Microscopic Heat Transfer Characteristics During Cooling of High Temperature Surface by a Falling Liquid Film

Yutaro Umehara, Tomio Okawa
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A003, August 4–6, 2021
Paper No: ICONE28-61737
DOI: https://doi.org/10.1115/ICONE28-61737
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Topics: Boiling, Cooling, Heat transfer, High temperature, Liquid films
Proceedings Papers

Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems

Hyeong-Yeon Lee, Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T06A004, August 4–6, 2021
Paper No: ICONE28-65552
DOI: https://doi.org/10.1115/ICONE28-65552
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Topics: Creep, Design, High temperature, Pipes, Piping systems, Pressure, Temperature
Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang
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, V003T11A007, August 4–6, 2021
Paper No: ICONE28-63388
DOI: https://doi.org/10.1115/ICONE28-63388
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics
Proceedings Papers

Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors

Ziling Zhou, Chuan Li, Nan Gui, Feng Xie, Yanwei Wen, Bin Shan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A016, August 4–6, 2021
Paper No: ICONE28-63539
DOI: https://doi.org/10.1115/ICONE28-63539
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Topics: Diffusion (Physics), Isotopes, Very high temperature reactors, Coolants, Graphite, Absorption, Desorption, Safety, Engineering prototypes, Fuels
Proceedings Papers

Characteristics of Debris From Simulated Molten Fuel Coolant Interaction Experiments

E. Hemanth Rao, Prabhat Kumar Shukla, Paulson Varghese, S. R. Polaki, E. Vetrivendan, Sanjay Kumar Das, D. Ponraju, S. Athmalingam, B. Venkatraman
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, V003T12A033, August 4–6, 2021
Paper No: ICONE28-65676
DOI: https://doi.org/10.1115/ICONE28-65676
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Topics: Accidents, Coolants, Fuels, Sodium fast reactors, Sodium, Heat, High temperature, Particulate matter, Damage, Evaporation
Proceedings Papers

Comparison of Pebble Bed Velocity Profiles Between High-Fidelity and Intermediate-Fidelity Codes

David Reger, Elia Merzari, Paolo Balestra, Sebastian Schunert, Yassin A. Hassan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A086, August 4–6, 2021
Paper No: ICONE28-65759
DOI: https://doi.org/10.1115/ICONE28-65759
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Topics: Accidents, Computational fluid dynamics, Cooling, Drag (Fluid dynamics), Flow (Dynamics), Fluids, Graphics processing units, High temperature, Modeling, Porosity
Proceedings Papers

Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads

Masato Murohara, Akira Yamazaki, Takuya Sato, Naoto Kasahara
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A072, August 4–6, 2021
Paper No: ICONE28-65553
DOI: https://doi.org/10.1115/ICONE28-65553
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Topics: Buckling, Reactor vessels, Failure, Design, Accidents, Deformation, Earthquakes, Fukushima nuclear disaster, Japan, 2011, High temperature, Nuclear reactor accidents
Proceedings Papers

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

Mohammad Alrwashdeh, Saeed A. Alameri
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, V001T05A014, August 4–5, 2020
Paper No: ICONE2020-16838
DOI: https://doi.org/10.1115/ICONE2020-16838
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Topics: Fuels, Particulate matter, Very high temperature reactors, Coating processes, Coatings, Cycles, Graphite, High temperature, Monte Carlo methods, Nuclear fuel cycle
Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

Leo A. Carrilho
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, V001T05A015, August 4–5, 2020
Paper No: ICONE2020-16872
DOI: https://doi.org/10.1115/ICONE2020-16872
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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants
Proceedings Papers

Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes

Jong Yeob Jung
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A007, August 4–5, 2020
Paper No: ICONE2020-16590
DOI: https://doi.org/10.1115/ICONE2020-16590
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Topics: Pressure, Creep, Fuels, Irradiation (Radiation exposure), Modeling, Cooling, Deformation, Flow (Dynamics), Heat, Heat transfer