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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
DOI: https://doi.org/10.1115/ICONE29-90295
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Topics: Containment, Graphite, Molten salt reactors, Thermal expansion
Proceedings Papers

Dynamic Analysis and Experimental Study of the Multi-Point Support Structure Based on Similar Theory Under Thermal Environment

Xi Deng, Qingsong Liu, Jianming Zhou, Chen Xi, Shuo Hou, Qiang Liu, Guangyao Lu, Xudong Wei, Liang Ni
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A059, August 8–12, 2022
Paper No: ICONE29-93497
DOI: https://doi.org/10.1115/ICONE29-93497
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Topics: Bearings, Clearances (Engineering), Computer simulation, Design, Dynamic analysis, Dynamics (Mechanics), High temperature, Manufacturing, Reliability, Risk
Proceedings Papers

Influence of Fuel Pellets’ Thermal Expansion on Temperature Feedback Regulation for Megawatt-Class Space Gas-Cooled Fast Reactor

Yuhao He, Dongdong Yuan, Kewei Ning, Xiaoyu Wang, Fulong Zhao, Sichao Tan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A071, August 4–6, 2021
Paper No: ICONE28-65504
DOI: https://doi.org/10.1115/ICONE28-65504
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Topics: Fast neutron reactors, Feedback, Fuels, Nuclear reactors, Temperature, Thermal expansion, Thermal stresses
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

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Yugao Ma, Minyun Liu, Wenbin Han, Biheng Xie, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A006, August 4–5, 2020
Paper No: ICONE2020-16100
DOI: https://doi.org/10.1115/ICONE2020-16100
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Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors
Proceedings Papers

Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA

Yanan He, Yingwei Wu, Shihuai Wang, Bowen Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A070, July 22–26, 2018
Paper No: ICONE26-82076
DOI: https://doi.org/10.1115/ICONE26-82076
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Topics: Fuels, Composite materials, Light water reactors, Accidents, Nuclear fission, Thermal conductivity, Thermal properties, Cladding systems (Building), Coolants, Enthalpy
Proceedings Papers

A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature

Brahim Nadri, Robert X. Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A005, July 22–26, 2018
Paper No: ICONE26-81167
DOI: https://doi.org/10.1115/ICONE26-81167
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Topics: Bifurcation, Boilers, High temperature, Superheaters, Creep, Metals, Fatigue, Fracture (Materials), Safety, Boiler tubes
Proceedings Papers

Neutronic Methodological Benchmarks With Simplified Geometries for the Gas Cooled Reactor Group Constant Generating Tools

E. Temesvari, B. Batki, M. Gren
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A009, July 22–26, 2018
Paper No: ICONE26-81427
DOI: https://doi.org/10.1115/ICONE26-81427
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Topics: Approximation, Doppler effect, Gas cooled reactors, Geometry, Leakage, Manufacturing, Modeling, Optical mirrors, Physics, Safety
Proceedings Papers

Structural Analysis and Manufacturing of HL-2M Vacuum Vessel and Support Structures

Yuncong Huang, Hong Ran, Zeng Cao, Jilai Hou, Binbin Song
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A006, July 22–26, 2018
Paper No: ICONE26-81273
DOI: https://doi.org/10.1115/ICONE26-81273
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Topics: Manufacturing, Structural analysis, Vacuum, Vessels, Stress, Tokamaks, Construction, Plasmas (Ionized gases), Rods, Dimensions
Proceedings Papers

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018
Paper No: ICONE26-81095
DOI: https://doi.org/10.1115/ICONE26-81095
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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue
Proceedings Papers

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Zehua Ma, Yingwei Wu, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A063, July 22–26, 2018
Paper No: ICONE26-81891
DOI: https://doi.org/10.1115/ICONE26-81891
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Topics: Deformation, Manufacturing, Sodium fast reactors, Temperature gradient, Computation, Displacement, Finite element model, Friction, Reliability, Rods
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
Proceedings Papers

Thermal Fatigue Test on Dissimilar Welded Joint Between Gr.91 and 304SS

Takashi Wakai, Sumio Kobayashi, Shoichi Kato, Masanori Ando, Hideki Takasho
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A008, July 2–6, 2017
Paper No: ICONE25-66099
DOI: https://doi.org/10.1115/ICONE25-66099
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Topics: Fatigue testing, Welded joints, Steel, Fatigue damage, Creep, Evaluation methods, Fatigue, Fatigue cracks, Finite element analysis, Alloys
Proceedings Papers

Preparation and Properties Investigation of Neutron Absorber Material Mo-Tb-Dy and Y-Tb-Dy Alloys

Junqiang Lu, Lei Chen, Congzhang Qiu, Weiyan Yang, Feifei Zhang, Ruifang Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A026, July 2–6, 2017
Paper No: ICONE25-66747
DOI: https://doi.org/10.1115/ICONE25-66747
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Topics: Alloys, Neutrons, Irradiation (Radiation exposure), Temperature, Corrosion, Atoms, Corrosion resistance, Density, Diluents, Displacement
Proceedings Papers

A Novel High-Power Magnetic Transmission System Based on Magnetic Conductivity Modulation Principle

Mo Tao, Jun Wu, Zhiwu Ke, Xianling Li, Yong Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A116, July 2–6, 2017
Paper No: ICONE25-67959
DOI: https://doi.org/10.1115/ICONE25-67959
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Topics: Electrical conductivity, Thermal conductivity, Torque, Permanent magnets, Rotors, Vibration, Deformation, Density, Gears, Nuclear power
Proceedings Papers

Out-of-Pile Properties Investigation of UO 2 -BeO Fuel Pellet

Jiwei Li, Yang Ding, Wentao Liu, Guangwen Bi, Ruirui Zhao, Qin Zhou
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A019, July 2–6, 2017
Paper No: ICONE25-66585
DOI: https://doi.org/10.1115/ICONE25-66585
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Topics: Fuels, Thermal conductivity, Elastic moduli, Thermal expansion, Uranium, Composite materials, Nuclear power stations, Sintering
Proceedings Papers

An Innovative Spherical Fuel Element to Inhibit the Infiltration of Liquid Fluoride Salt in Molten Salt Reactor

Yajuan Zhong, Jun Lin, Liujun Xu, Haitao Jiang, Zhiyong Zhu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A023, July 2–6, 2017
Paper No: ICONE25-66639
DOI: https://doi.org/10.1115/ICONE25-66639
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Topics: Fuels, Molten salt reactors, Graphite, Shells, Density, Stress, Design, Operating temperature, Porosity, Safety
Proceedings Papers

Nonlinear Finite Element Analysis of Class 1 Pressure Vessels

Mingya Chen, Weiwei Yu, Jinhua Shi, Feng Lu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A004, July 2–6, 2017
Paper No: ICONE25-66910
DOI: https://doi.org/10.1115/ICONE25-66910
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Topics: Finite element analysis, Pressure vessels, Stress, Design, Nozzles, Elastic analysis, Failure, Pipes, Reactor vessels, ASME Standards
Proceedings Papers

Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop

Leitai Shi, Guanghui Su, Tan Bing, Ronghua Chen, Wenxi Tian, Suizheng Qiu, Junmei Wu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A017, July 2–6, 2017
Paper No: ICONE25-66261
DOI: https://doi.org/10.1115/ICONE25-66261
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Topics: Cooling, Flow (Dynamics), Heat sinks, Heat transfer, Heating, Natural convection, Pumps, Temperature, Test facilities, Thermal expansion
Proceedings Papers

Numerical Simulation of Different Sizes Missing Pellet Surface Effects on Thermal-Mechanical Behaviors in Nuclear Fuel Rods

Changbing Tang, Yongjun Jiao, Wenjie Li, Tao Qing, Yifei Miao, Ping Chen
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A008, June 26–30, 2016
Paper No: ICONE24-60116
DOI: https://doi.org/10.1115/ICONE24-60116
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Topics: Computer simulation, Fuel rods, Cladding systems (Building), Irradiation (Radiation exposure), Nuclear fission, Stress, Creep, Temperature, Compressive stress, Failure