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Proceedings Papers

The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite

Yuxin Guan, Yingjie Zhan, Shuiyong Wang, Qingwu Wang, Wenxin Ti, Bing Gong
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A028, August 8–12, 2022
Paper No: ICONE29-91966
https://doi.org/10.1115/ICONE29-91966
View Paper titled, The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite
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Topics: Graphite, Size effect, Surface roughness, Tensile strength
Proceedings Papers

Experimental Study on Dynamic Tensile Strength of Graphite

Dongqing Tian, Li Shi, Libin Sun, Ke Shen, Kun Xu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A019, August 8–12, 2022
Paper No: ICONE29-90670
https://doi.org/10.1115/ICONE29-90670
View Paper titled, Experimental Study on Dynamic Tensile Strength of Graphite
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Topics: Graphite, Stress-strain curves, Tensile strength
Proceedings Papers

Volume Change Analysis of Primary Loop in a Small Modular Thorium-Based Molten Salt Reactor

Guifeng Zhu, Yang Zou, Rui Yan, Wei Guo, Xuzhong Kang, Tiangui Xu, Pu Yang, Bo Zhou
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A004, August 8–12, 2022
Paper No: ICONE29-90295
https://doi.org/10.1115/ICONE29-90295
View Paper titled, Volume Change Analysis of Primary Loop in a Small Modular Thorium-Based Molten Salt Reactor
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Topics: Containment, Graphite, Molten salt reactors, Thermal expansion
Proceedings Papers

Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography

Renjie Liu, Yuewen Sun, Tianchen Zeng, Ximing Liu, Libin Sun, Li Shi, Peng Cong
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A039, August 8–12, 2022
Paper No: ICONE29-92345
https://doi.org/10.1115/ICONE29-92345
View Paper titled, Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography
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Topics: Carbon, Computerized tomography, Flaw detection, Gas cooled reactors, Graphite, High temperature
Proceedings Papers

Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite

Tianchen Zeng, Yuewen Sun, Peng Cong
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A037, August 8–12, 2022
Paper No: ICONE29-92295
https://doi.org/10.1115/ICONE29-92295
View Paper titled, Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite
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Topics: Damage, Graphite, Simulation
Proceedings Papers

An Experimental Study on the Retention of Graphite Dust Aerosol in Pool Scrubbing and the Possible Application in HTGRs

Yating Wang, Yiyang Zhang, Zhu Fang, Xinxin Wu
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A015, August 8–12, 2022
Paper No: ICONE29-92561
https://doi.org/10.1115/ICONE29-92561
View Paper titled, An Experimental Study on the Retention of Graphite Dust Aerosol in Pool Scrubbing and the Possible Application in HTGRs
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Topics: Aerosols, Decontamination, Dust, Graphite, Very high temperature reactors, Water
Proceedings Papers

Pulverization and Spheroidization of Natural Graphite Powder for The Matrix Graphite in High-Temperature Gas-Cooled Reactors

Xinlei Cao, Zhenming Lu, Yuxiao Feng, Juan Bai, Bing Liu, Ke Shen
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A096, August 8–12, 2022
Paper No: ICONE29-92524
https://doi.org/10.1115/ICONE29-92524
View Paper titled, Pulverization and Spheroidization of Natural Graphite Powder for The Matrix Graphite in High-Temperature Gas-Cooled Reactors
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Topics: Graphite, Very high temperature reactors
Proceedings Papers

A Numerical Study on the Behaviors of Graphite Aerosol in the Containment During a Water Ingress Accident of High Temperature Gas-Cooled Reactors

Zhu Fang, Yiyang Zhang, Yating Wang, Zhikai You, Libin Sun, Xinxin Wu
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A055, August 8–12, 2022
Paper No: ICONE29-92955
https://doi.org/10.1115/ICONE29-92955
View Paper titled, A Numerical Study on the Behaviors of Graphite Aerosol in the Containment During a Water Ingress Accident of High Temperature Gas-Cooled Reactors
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Topics: Accidents, Aerosols, Containment, Dust, Graphite, Very high temperature reactors, Water
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
https://doi.org/10.1115/ICONE28-63633
View Paper titled, Study on Dehumidification of Carbon Materials Based on Thermogravimetry
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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
https://doi.org/10.1115/ICONE28-63539
View Paper titled, Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors
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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
https://doi.org/10.1115/ICONE28-64344
View Paper titled, Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming
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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
https://doi.org/10.1115/ICONE2020-16838
View Paper titled, Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors
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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
https://doi.org/10.1115/ICONE2020-16340
View Paper titled, CFD-DEM Simulations of Graphite Particle Collisions in Opposed Jet Mill
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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
https://doi.org/10.1115/ICONE2020-16058
View Paper titled, Modeling the Molten Salt Reactor Experiment With the GOTHIC Code
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Topics: Design, Modeling, Molten salt reactors, Heat, Fuels, Neutrons, Transients (Dynamics), Flow (Dynamics), Fluids, Nuclear fission
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
https://doi.org/10.1115/ICONE26-82598
View Paper titled, Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles
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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
https://doi.org/10.1115/ICONE26-81768
View Paper titled, Research on Heat Transfer Characteristics of the Thermometric Sphere in HTR-10
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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
https://doi.org/10.1115/ICONE26-81792
View Paper titled, A Numerical Study of Particle Deposition Through Fuel Pebble Bed in HTGR
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Topics: Fuels, Particulate matter, Very high temperature reactors, Dust, Graphite, Abrasion, Accidents, Flow (Dynamics), Safety, Trajectories (Physics)
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
https://doi.org/10.1115/ICONE26-81887
View Paper titled, TREAT Transient Modeling and Impact of Graphite Thermal Scattering
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Topics: Electromagnetic scattering, Graphite, Modeling, Radiation scattering, Scattering (Physics), Transients (Dynamics), Simulation, Temperature, Fuels, Cross section (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
https://doi.org/10.1115/ICONE26-81174
View Paper titled, Effect of Al 2 O 3 and SiC Content in Pack Cementation Powders on the Microstructure of SiC Coatings on HTR Graphite Spheres
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Topics: Coatings, Graphite, Sintering, Bonding, Oxidation, Porosity, Raman spectroscopy, Raw materials, Scanning electron microscopy, Vacuum
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
https://doi.org/10.1115/ICONE26-81090
View Paper titled, Modelling and Simulation Activities in Support of the UK Nuclear R&D Programme on Digital Reactor Design
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Topics: Design, Modeling, Simulation, Pressurized water reactors, Physics, Bricks, Graphite, Nuclear design