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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

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

Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming

Junyi Li, Zhe Dong, Bowen Li
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A030, August 4–6, 2021
Paper No: ICONE28-64344
DOI: https://doi.org/10.1115/ICONE28-64344
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Topics: Dynamic modeling, Hydrogen production, Methane, Steam reforming, Molten salt reactors, Steam, Thermal energy, Catalysts, Coolants, Electric power generation
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

CFD-DEM Simulations of Graphite Particle Collisions in Opposed Jet Mill

Sifan Peng, Yujia Liu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang
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, V001T03A008, August 4–5, 2020
Paper No: ICONE2020-16340
DOI: https://doi.org/10.1115/ICONE2020-16340
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Topics: Computational fluid dynamics, Discrete element methods, Engineering simulation, Graphite, Particle collisions, Simulation, Particulate matter, Flow (Dynamics), Collisions (Physics), Air flow
Proceedings Papers

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

Rodney Harvill, Jeff Lane, John Link, Anita Gates, Tom Kindred
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A002, August 4–5, 2020
Paper No: ICONE2020-16058
DOI: https://doi.org/10.1115/ICONE2020-16058
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Topics: Design, Modeling, Molten salt reactors, Heat, Fuels, Neutrons, Transients (Dynamics), Flow (Dynamics), Fluids, Nuclear fission
Proceedings Papers

Modelling and Simulation Activities in Support of the UK Nuclear R&D Programme on Digital Reactor Design

B. Lindley, D. Allen, J. Lillington, A. Smethurst, P. Smith, D. Bowman, L. Dwyer, K. Lai, A. Levers, K. Vikhorev, D. Litskevich, B. Merk, E. Patelli, E. Patterson, M. Bankhead, A. Peakman, S. de Haas, C. Jackson, J. Draup, E. Galenne, G. Parks, E. Shwageraus, M. D. Eaton
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A004, July 22–26, 2018
Paper No: ICONE26-81090
DOI: https://doi.org/10.1115/ICONE26-81090
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Topics: Design, Modeling, Simulation, Pressurized water reactors, Physics, Bricks, Graphite, Nuclear design
Proceedings Papers

TREAT Transient Modeling and Impact of Graphite Thermal Scattering

Nina C. Sorrell, Ayman I. Hawari
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A062, July 22–26, 2018
Paper No: ICONE26-81887
DOI: https://doi.org/10.1115/ICONE26-81887
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Topics: Electromagnetic scattering, Graphite, Modeling, Radiation scattering, Scattering (Physics), Transients (Dynamics), Simulation, Temperature, Fuels, Cross section (Physics)
Proceedings Papers

Numerical Investigation of Mass Mixing in the Reactor Core of a Pebble Bed HTGR

Wei Lu, Xiaowei Li, Xinxin Wu
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A022, July 22–26, 2018
Paper No: ICONE26-81722
DOI: https://doi.org/10.1115/ICONE26-81722
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Topics: Very high temperature reactors, Fuels, Flow (Dynamics), Oxidation, Accidents, Computer simulation, Coolants, Corrosion, Diffusion (Physics), Gases
Proceedings Papers

Influence Factors on Moisture Absorption Process of Carbon Material in HTGR

Jun Li, Huaqiang Yin, Xuedong He
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A016, July 22–26, 2018
Paper No: ICONE26-81412
DOI: https://doi.org/10.1115/ICONE26-81412
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Topics: Absorption, Carbon, Very high temperature reactors, Boron, Corrosion, Diffusion (Physics), Graphite, High temperature, Temperature
Proceedings Papers

Radiation Protection Calculation and Optimization for Shielding Design Around the Refueling Pipelines of HTR-PM

Sheng Fang, Hong Li, Wenqian Li
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A024, July 22–26, 2018
Paper No: ICONE26-82581
DOI: https://doi.org/10.1115/ICONE26-82581
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Topics: Design, Optimization, Pipelines, Radiation (Physics), Fuels, Steel, Cables, China, Concrete walls, Cycles
Proceedings Papers

Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions

Hao Qin, Chenglong Wang, Suizheng Qiu, Dalin Zhang, Wenxi Tian, Guanghui Su
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A023, July 22–26, 2018
Paper No: ICONE26-81728
DOI: https://doi.org/10.1115/ICONE26-81728
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Topics: Molten salt reactors, Transients (Dynamics), Absorption, Accidents, Corrosion, Dynamic response, Graphite, High temperature, Steady state
Proceedings Papers

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

R. Lo Frano, M. Puccini, E. Stefanelli, M. Luppichini, C. Grima, S. Vitolo, D. Aquaro, S. Malquori, S. De Sanctis
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A030, July 22–26, 2018
Paper No: ICONE26-82598
DOI: https://doi.org/10.1115/ICONE26-82598
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Topics: Manufacturing, Casting, Collaboration, Graphite, High temperature, Lithium, Microfluidics, Sprays, Temperature
Proceedings Papers

Research on Heat Transfer Characteristics of the Thermometric Sphere in HTR-10

Shiyan Sun, Youjie Zhang, Yanhua Zheng, Xiang Fang, Xiaoyong Yang
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A015, July 22–26, 2018
Paper No: ICONE26-81768
DOI: https://doi.org/10.1115/ICONE26-81768
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Topics: Heat transfer, Temperature, Graphite, Metals, Thermal equilibrium, Very high temperature reactors, Wire, Computational fluid dynamics, Construction, Convection
Proceedings Papers

A Numerical Study of Particle Deposition Through Fuel Pebble Bed in HTGR

Qi Sun, Gang Zhao, Wei Peng, Suyuan Yu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A054, July 22–26, 2018
Paper No: ICONE26-81792
DOI: https://doi.org/10.1115/ICONE26-81792
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Topics: Fuels, Particulate matter, Very high temperature reactors, Dust, Graphite, Abrasion, Accidents, Flow (Dynamics), Safety, Trajectories (Physics)
Proceedings Papers

Effect of Al 2 O 3 and SiC Content in Pack Cementation Powders on the Microstructure of SiC Coatings on HTR Graphite Spheres

Hongsheng Zhao, Ping Zhou, Ziqiang Li, Xiaoxue Liu, Kaihong Zhang, Taowei Wang, Bin Wu, Bing Liu
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A008, July 22–26, 2018
Paper No: ICONE26-81174
DOI: https://doi.org/10.1115/ICONE26-81174
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Topics: Coatings, Graphite, Sintering, Bonding, Oxidation, Porosity, Raman spectroscopy, Raw materials, Scanning electron microscopy, Vacuum
Proceedings Papers

Non-LWR Model Development for the MELCOR Code

Larry Humphries, Brad Beeny, David Louie, Hossein Esmaili, Michael Salay
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A056, July 22–26, 2018
Paper No: ICONE26-82415
DOI: https://doi.org/10.1115/ICONE26-82415
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Topics: Light water reactors, Model development, Fluids, Modeling, Molten salt reactors, Sodium, Sodium fast reactors, Accidents, Graphite, Very high temperature reactors
Proceedings Papers

A Numerical Study on Graphite Dust Deposition on Steam Generator Tubes in the High-Temperature Gas-Cooled Reactor (HTGR)

Mingzhe Wei, Yiyang Zhang, Zhu Fang, Xinxin Wu, Libin Sun
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A024, July 22–26, 2018
Paper No: ICONE26-82043
DOI: https://doi.org/10.1115/ICONE26-82043
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Topics: Boilers, Dust, Graphite, Very high temperature reactors, Particulate matter, Adhesion, Finite element methods, Simulation, Accidents, Collisions (Physics)
Proceedings Papers

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

Jinhua Wang, Bing Wang, Bin Wu, Yue Li, Haitao Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A001, July 22–26, 2018
Paper No: ICONE26-81022
DOI: https://doi.org/10.1115/ICONE26-81022
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Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines
Proceedings Papers

The Compatibility of Nuclear Graphite With Molten Salt in the Molten Salt Reactor

Zhoutong He, Hui Tang, Can Zhang, Yantao Gao, Huihao Xia, Xingtai Zhou
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A026, July 22–26, 2018
Paper No: ICONE26-82065
DOI: https://doi.org/10.1115/ICONE26-82065
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Topics: Graphite, Molten salt reactors, Temperature, Strength (Materials), Thermal expansion, Coolants, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressure