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Proceedings Papers

TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme

Junxiao Zhang, Songyang Liu, Junhao Xie, Tian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136107
https://doi.org/10.1115/ICONE31-136107
View Paper titled, TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme
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Topics: Fuels, High temperature, Particulate matter, Nuclear fission, Temperature, Very high temperature reactors, Diffusion (Physics), Failure, Flow (Dynamics), Safety
Proceedings Papers

Study on the Effective Diffusion Coefficient of Inert Gases in Porous Graphite Materials

Rui Nie, Yu Wang, Ziling Zhou, Weihua Zhang, Feng Xie, Hong Li, Liqiang Wei, Zhixiang Fan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A042, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135581
https://doi.org/10.1115/ICONE31-135581
View Paper titled, Study on the Effective Diffusion Coefficient of Inert Gases in Porous Graphite Materials
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Topics: Diffusion (Physics), Fuels, Gases, Graphite, Very high temperature reactors
Proceedings Papers

A Nonlocal Meso-Scale Damage Model for Nuclear Graphite

Yan Ma, Yue Qian, Yuchen Hao, Musen Lin, Yue Li, Jinhua Wang, Haitao Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A029, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134775
https://doi.org/10.1115/ICONE31-134775
View Paper titled, A Nonlocal Meso-Scale Damage Model for Nuclear Graphite
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Topics: Damage, Failure, Graphite
Proceedings Papers

Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM

Qianye Yang, Nan Gui, Jiyuan Tu, Shengyao Jiang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131880
https://doi.org/10.1115/ICONE31-131880
View Paper titled, Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM
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Topics: Design, Eigenvalues, Fuels, Modeling, Graphite, Simulation, High temperature, Nuclear fuels, Particulate matter, Safety
Proceedings Papers

Preparation of SiC Composite Coating on the Surface of Graphite Spheres in VHTR

Hui Yang, Hongsheng Zhao, Kaihong Zhang, Xing Cheng, Ziqiang Li, Yue Wang, Bing Liu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A028, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134744
https://doi.org/10.1115/ICONE31-134744
View Paper titled, Preparation of SiC Composite Coating on the Surface of Graphite Spheres in VHTR
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Topics: Coatings, Composite materials, Graphite, Oxidation, Silicon carbide, Very high temperature reactors
Proceedings Papers

The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme

Songyang Liu, Xuelin Li, Yong Luo, Wei Liu, Qin Zhou, Cheng Gu, Tian Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133310
https://doi.org/10.1115/ICONE31-133310
View Paper titled, The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
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Topics: Accidents, Steady state, Fuels, Temperature, China, Equilibrium (Physics), Graphite, Construction, Coolants, Design
Proceedings Papers

Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor

Jipu Hu, Yuyang Shen, Ruixiang Wang, Kuaiyuan Feng, Lei Lou, Hui Guo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-124442
https://doi.org/10.1115/ICONE31-124442
View Paper titled, Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor
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Topics: Accidents, Ceramics, Computer software, Coolants, Design, Engineering simulation, Flow (Dynamics), Fluids, Fuels, Graphite
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
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Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

Impact of Narrow Gaps on Graphite Component Lifespan in Small Modular Molten Salt Reactors

Qi Wang, Yu Zhong, Chenggang Yu, Wei Guo, Jingen Chen, Zhichao Wang, Qiang Sun
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A072, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136988
https://doi.org/10.1115/ICONE31-136988
View Paper titled, Impact of Narrow Gaps on Graphite Component Lifespan in Small Modular Molten Salt Reactors
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Topics: Graphite, Manufacturing, Molten salt reactors
Proceedings Papers

Study on Radionuclide Desorption in Matrix Graphite Under Accident Conditions

Wei Xu, Jian Li
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A088, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135804
https://doi.org/10.1115/ICONE31-135804
View Paper titled, Study on Radionuclide Desorption in Matrix Graphite Under Accident Conditions
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Topics: Accidents, Desorption, Graphite, Oxidation, Radioisotopes, Very high temperature reactors
Proceedings Papers

Experimental Investigation on the Gasification Kinetics of Irradiated A3-3 Matrix Graphite

Weishuai Wang, Naizhe Zhang, Xuegang Liu, Feng Xie
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133398
https://doi.org/10.1115/ICONE31-133398
View Paper titled, Experimental Investigation on the Gasification Kinetics of Irradiated A3-3 Matrix Graphite
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Topics: Fuel gasification, Graphite
Proceedings Papers

Reconstruction of 3D Nuclear Graphite Based on Generative Adversarial Neural Networks With Gradient Penalty

Lei Peng, Zhiyong Liu, Pengyu Wang, Hao Liu, Huang Zhang, Huaqiang Yin, Xuedong He, Tao Ma
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134733
https://doi.org/10.1115/ICONE31-134733
View Paper titled, Reconstruction of 3D Nuclear Graphite Based on Generative Adversarial Neural Networks With Gradient Penalty
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Topics: Artificial neural networks, Graphite
Proceedings Papers

An Experimental Study on the Scrubbing Characteristics of Graphite Dust Aerosol in HTGRs

Yating Wang, Yiyang Zhang, Zhikai You, Shumiao Zhao, Zhu Fang, Libin Sun
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134288
https://doi.org/10.1115/ICONE31-134288
View Paper titled, An Experimental Study on the Scrubbing Characteristics of Graphite Dust Aerosol in HTGRs
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Topics: Aerosols, Decontamination, Dust, Graphite, Very high temperature reactors, Water
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
Publisher: American Society of Mechanical Engineers
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
Publisher: American Society of Mechanical Engineers
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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
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