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Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A007, August 4–6, 2021

Paper No: ICONE28-63388

DOI: https://doi.org/10.1115/ICONE28-63388

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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics

Proceedings Papers

Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field

Hua Li, Ti Yue, Fawen Zhu, Yuan Peng, Yun Li, Chunlan Huang, Youjia Zhang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A017, August 4–6, 2021

Paper No: ICONE28-65776

DOI: https://doi.org/10.1115/ICONE28-65776

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Topics: Additive manufacturing, Design, Fuels, Manufacturing, Nuclear fuels

Proceedings Papers

Risk Analysis of Gasification Process of Nuclear Fuel Manufacturing Facilities Based on FTA

Xiaowei Yang, Dan Lyu, Ji Que, Yuntao Liu, Shangui Zhao

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A006, August 4–6, 2021

Paper No: ICONE28-63648

DOI: https://doi.org/10.1115/ICONE28-63648

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Topics: Fuel gasification, Nuclear fuels, Production facilities, Risk analysis

Proceedings Papers

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Hui Fu, Daogang Lu, Yu Liu

Paper No: ICONE28-64082

DOI: https://doi.org/10.1115/ICONE28-64082

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Topics: Alloys, Safety, Earthquakes, Collisions (Physics), Computer simulation, Coolants, Finite element methods, Leakage, Neutrons, Nuclear fuels

Proceedings Papers

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Qian Ma, Zhitong Yu, Peiwei Sun, Yuwen Jia, Shifa Wu

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A043, August 4–6, 2021

Paper No: ICONE28-64459

DOI: https://doi.org/10.1115/ICONE28-64459

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Topics: Adaptive control, Design, Nuclear reactors, Control systems, Feedback, Fuels, Transfer functions, Ceramics, Control equipment, Dynamic models

Proceedings Papers

Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle

Thien Nguyen, Rodolfo Vaghetto, Yassin Hassan

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A029, August 4–5, 2020

Paper No: ICONE2020-16570

DOI: https://doi.org/10.1115/ICONE2020-16570

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Topics: Fuel rods, Turbulence, Flow (Dynamics), Fuels, Wire, Coolants, Heat transfer, Manufacturing, Cladding systems (Building), Deformation

Proceedings Papers

Finite Element Model to Simulate the Spacer Grid Buckling Characteristics

Youngik Yoo, Joongjin Kim, Kyongbo Eom, Hyeongkoo Kim

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, V001T05A002, August 4–5, 2020

Paper No: ICONE2020-16082

DOI: https://doi.org/10.1115/ICONE2020-16082

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Topics: Buckling, Finite element model, Fuel rods, Manufacturing, Mechanical behavior, Nuclear fuels, Compression, Drag (Fluid dynamics), Impact testing, Mechanical properties

Proceedings Papers

Study on the Spacer Grid Dynamic Crush Strength According to Cell Sizes

Jooyoung Ryu, Hangil Woo, Chaeyoung Nam, Youngik Yoo, Namgyu Park, Seungjae Lee

Paper No: ICONE2020-16149

DOI: https://doi.org/10.1115/ICONE2020-16149

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Topics: Accidents, Additive manufacturing, Buckling, Cladding systems (Building), Coolants, Deformation, Failure, Flow (Dynamics), Fuel rods, Fuels

Proceedings Papers

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Changbing Tang, Yongjun Jiao, Yuanming Li, Yi Zhou, Kun Zhang

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A036, August 4–5, 2020

Paper No: ICONE2020-16387

DOI: https://doi.org/10.1115/ICONE2020-16387

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Topics: Cladding systems (Building), Computer simulation, Computer software, Fuel rods, Fuels, Stress, Failure, Pressure, Simulation, Transients (Dynamics)

Proceedings Papers

Preventing Nuclear Fuel Material Adhesion on Glove Box Components Using Nanoparticle Coating

Tomoomi Segawa, Koichi Kawaguchi, Katsunori Ishii, Masahiro Suzuki, Joji Tachihara, Kiyoto Takato, Takatoshi Okita, Hiroshi Satone, Michitaka Suzuki

Paper No: ICONE2020-16215

DOI: https://doi.org/10.1115/ICONE2020-16215

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Topics: Adhesion, Coating processes, Coatings, Nanoparticles, Nuclear fuels

Proceedings Papers

Modelling of the H2020 INSPYRE Fuel Creep Experiment

Alexander Fedorov, Kevin Zwijsen, Sander van Til

Paper No: ICONE2020-16231

DOI: https://doi.org/10.1115/ICONE2020-16231

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Topics: Computer simulation, Creep, Fuels, Modeling, Nuclear fuels

Proceedings Papers

A Critical Experimental Study of Bubble Effect in the Process of Spent Fuel Dissolving

Zhou Xiaoping, Liang Shuhong, Xia Zhaodong

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A021, July 22–26, 2018

Paper No: ICONE26-81644

DOI: https://doi.org/10.1115/ICONE26-81644

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Topics: Bubbles, Spent nuclear fuels, Nuclear fuels, Absorption, Fuels, Heat, Leakage, Neutrons, Safety, Simulation

Proceedings Papers

The Quality Experience Feedback in Nuclear Fuel Manufacture

Tong MengYao, Li FangGang

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A004, July 22–26, 2018

Paper No: ICONE26-81374

DOI: https://doi.org/10.1115/ICONE26-81374

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Topics: Feedback, Nuclear fuels, Manufacturing, Filters, Flow (Dynamics), Fuels, Quality management

Proceedings Papers

Main Evolutions of the RCC-C Design and Construction Code for Fuel Assemblies Since 2015

Marc Ton-That, Christine Vauglin, Gilbert Trillon

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A005, July 22–26, 2018

Paper No: ICONE26-81436

DOI: https://doi.org/10.1115/ICONE26-81436

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Topics: Construction, Design, Fuels, Pressurized water reactors, Manufacturing, Nuclear fuels, Fire, In-service inspection, Inspection, Regulations

Proceedings Papers

EPR: Burnable Absorber Optimization

Michal Zeman, Radek Škoda, Jiří Závorka

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A011, July 22–26, 2018

Paper No: ICONE26-81215

DOI: https://doi.org/10.1115/ICONE26-81215

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Topics: Optimization, Fuels, European pressurized reactors, Nuclear fuel cycle, Nuclear fuels

Proceedings Papers

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Muhammad Altahhan, Noah McFerran, Jonathan Morrell, Maria Avramova

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A031, July 22–26, 2018

Paper No: ICONE26-81464

DOI: https://doi.org/10.1115/ICONE26-81464

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Topics: Ceramic matrix composites, Cladding systems (Building), Silicon, Fuels, Pressurized water reactors, Critical heat flux, Design, Manufacturing, Pressure, Boiling

Proceedings Papers

Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR

Tangtao Feng, Wenxi Tian, Ping Song, Jun Wang, Mingjun Wang, G. H. Su, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A049, July 22–26, 2018

Paper No: ICONE26-81738

DOI: https://doi.org/10.1115/ICONE26-81738

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Topics: Fuel rods, Accidents, Computer software, High temperature, Hydrogen, Nuclear fuels, Numerical analysis, Temperature, Transients (Dynamics), Tungsten

Proceedings Papers

Flow and Temperature Fields Measurement Inside Rod Bundle by the Combined Use of PIV and LIF Technique

Xing Li, Sichao Tan, Zhengpeng Mi, Peiyao Qi, Yunlong Huang

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A034, July 22–26, 2018

Paper No: ICONE26-81526

DOI: https://doi.org/10.1115/ICONE26-81526

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Topics: Flow (Dynamics), Fuel rods, Temperature, Coolants, Design, Flow measurement, Fluid mechanics, Fluorescence, Geometry, Heat

Proceedings Papers

Multiphysics Modeling of Fabrication Methods’ Effect on UO 2 -BeO Composite Fuels’ Performance

Wei Zhou, Wenzhong Zhou

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A026, July 22–26, 2018

Paper No: ICONE26-81429

DOI: https://doi.org/10.1115/ICONE26-81429

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Topics: Composite materials, Fuels, Manufacturing, Modeling, Particulate matter, Thermal conductivity, Grain size, Accidents, Microcracks, Nuclear fission

Proceedings Papers

Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal

Susumu Yamashita, Hiroyuki Yoshida

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A033, July 22–26, 2018

Paper No: ICONE26-82088

DOI: https://doi.org/10.1115/ICONE26-82088

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Topics: Computer simulation, Fuels, Nuclear reactors, Accidents, Melting, Alpha decay, Cladding systems (Building), Computational fluid dynamics, Fukushima nuclear disaster, Japan, 2011, Heat

2 3 4 5

NARROW

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field

Risk Analysis of Gasification Process of Nuclear Fuel Manufacturing Facilities Based on FTA

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle

Finite Element Model to Simulate the Spacer Grid Buckling Characteristics

Study on the Spacer Grid Dynamic Crush Strength According to Cell Sizes

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Preventing Nuclear Fuel Material Adhesion on Glove Box Components Using Nanoparticle Coating

Modelling of the H2020 INSPYRE Fuel Creep Experiment

A Critical Experimental Study of Bubble Effect in the Process of Spent Fuel Dissolving

The Quality Experience Feedback in Nuclear Fuel Manufacture

Main Evolutions of the RCC-C Design and Construction Code for Fuel Assemblies Since 2015

EPR: Burnable Absorber Optimization

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR

Flow and Temperature Fields Measurement Inside Rod Bundle by the Combined Use of PIV and LIF Technique

Multiphysics Modeling of Fabrication Methods’ Effect on UO 2 -BeO Composite Fuels’ Performance

Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal

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