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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

DOI: https://doi.org/10.1115/ICONE29-91966

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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

DOI: https://doi.org/10.1115/ICONE29-90670

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Topics: Graphite, Stress-strain curves, Tensile strength

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

DOI: https://doi.org/10.1115/ICONE29-92955

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Topics: Accidents, Aerosols, Containment, Dust, Graphite, Very high temperature reactors, Water

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

DOI: https://doi.org/10.1115/ICONE29-92561

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Topics: Aerosols, Decontamination, 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

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

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

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

NARROW

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

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

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

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

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

Experimental Study on Dynamic Tensile Strength of Graphite

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

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

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

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

Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming

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

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

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

TREAT Transient Modeling and Impact of Graphite Thermal Scattering

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

Influence Factors on Moisture Absorption Process of Carbon Material in HTGR

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

Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

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