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Proceedings Papers

Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A007, August 8–12, 2022

Paper No: ICONE29-89223

DOI: https://doi.org/10.1115/ICONE29-89223

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Topics: Nuclear fuel cycle, Pressurized water reactors

Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022

Paper No: ICONE29-89461

DOI: https://doi.org/10.1115/ICONE29-89461

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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods

Proceedings Papers

Modelica Based Economic Analysis of Nuclear Fuel Cycle

Jie Liu, Xiang Wang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 8–12, 2022

Paper No: ICONE29-91600

DOI: https://doi.org/10.1115/ICONE29-91600

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Topics: Economic analysis, Economics , Nuclear fuel cycle

Proceedings Papers

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

Xiaoqian Zhang, Pengtao Fu

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A034, August 8–12, 2022

Paper No: ICONE29-92822

DOI: https://doi.org/10.1115/ICONE29-92822

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Topics: Boiling, Coolants, Corrosion, Pressurized water reactors, Radioisotopes, Cycles, Circuits, Maintenance, Shapes, Cobalt

Proceedings Papers

High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method

Kai Gao, Wendong Feng, Xiaojun Yan, Xiaobin Guo, Xiaoyan Cui, Xiliang Guo

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A009, August 8–12, 2022

Paper No: ICONE29-90716

DOI: https://doi.org/10.1115/ICONE29-90716

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Topics: Aluminum, Cements (Adhesives), Exhaust systems, Glass, High temperature, Ion exchange, Nuclear fuel cycle, Phase transition temperature, Raw materials, Sewage

Proceedings Papers

Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor

Jinggang Xu, Qin Zeng, Sheng Wang, Huaihuai Wang, Junjie Zhou, Yangbin Xiong, Jingchen Yang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A007, August 8–12, 2022

Paper No: ICONE29-90643

DOI: https://doi.org/10.1115/ICONE29-90643

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Topics: Magnetic fusion, Modeling, Nuclear fuel cycle

Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto

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, V001T04A010, August 4–6, 2021

Paper No: ICONE28-64347

DOI: https://doi.org/10.1115/ICONE28-64347

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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature

Proceedings Papers

Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities

Dan Lyu, Xiao-wei Yang, Yan Lu, Shi-jun Wang, Chun-yan Xu

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A005, August 4–6, 2021

Paper No: ICONE28-63354

DOI: https://doi.org/10.1115/ICONE28-63354

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Topics: Failure, Failure data, Nuclear fuel cycle, Valves

Proceedings Papers

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang

Paper No: ICONE28-65406

DOI: https://doi.org/10.1115/ICONE28-65406

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Topics: Ceramics, Fast neutron reactors, High temperature, Neutrons, Nuclear fuel cycle, Physics, Spent nuclear fuels

Proceedings Papers

Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR

Baorui Zhang, Zhaoyang Xia, Zhiwei Zhou

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, V003T08A017, August 4–6, 2021

Paper No: ICONE28-65076

DOI: https://doi.org/10.1115/ICONE28-65076

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Topics: Ceramics, China, Computational fluid dynamics, Coolants, Design, Discrete element methods, Flow (Dynamics), Fusion reactors, Helium, Modeling

Proceedings Papers

A Beyond Design Basis Earthquake Study of Operating Nuclear Fuel Cycle Facilities

Li Liang, Pan Rong, Zhu Xiuyun, Ren Guopeng

Paper No: ICONE28-64514

DOI: https://doi.org/10.1115/ICONE28-64514

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Topics: Design, Earthquakes, Nuclear fuel cycle, Safety

Proceedings Papers

The Safety of Nuclear Fuel Cycle Facilities in China After the Fukushima Accident

Ji Que, Xiao-wei Yang, Yun-tao Liu, Shan-gui Zhao, Hong Shen, Tian-Shu Liu

Paper No: ICONE28-64258

DOI: https://doi.org/10.1115/ICONE28-64258

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Topics: China, Fukushima nuclear disaster, Japan, 2011, Nuclear fuel cycle, Safety

Proceedings Papers

Thermal-Hydraulic Design Support and Safety Analyses of SEALER UK Demo

Kevin Zwijsen, Heleen Uitslag-Doolaard, Ferry Roelofs, Janne Wallenius

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A028, August 4–5, 2020

Paper No: ICONE2020-16526

DOI: https://doi.org/10.1115/ICONE2020-16526

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Topics: Computational fluid dynamics, Design, Safety, Computer simulation, Energy generation, Engineering simulation, Flow (Dynamics), Freezing, Geometry, Light water reactors

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

Experimental Setup for Non-Contact Displacement Measurement of Nuclear Waste via Electromagnetic Waves

Mauro Cappelli, Vincenzo Surrenti

Paper No: ICONE2020-16653

DOI: https://doi.org/10.1115/ICONE2020-16653

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Topics: Cables, Displacement measurement, Electromagnetic radiation, Radioactive wastes, Sensors, Computer simulation, Design, Electromagnetic fields, Energy consumption, Engineering prototypes

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

Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A005, July 22–26, 2018

Paper No: ICONE26-81082

DOI: https://doi.org/10.1115/ICONE26-81082

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Topics: China, Construction, Cross section (Physics), Discrete element methods, Engineering simulation, Flow (Dynamics), Fuels, High temperature, Matlab, Nuclear fuel cycle

Proceedings Papers

Overview of the U.S. Department of Energy Advanced Waste Forms Development

Kimberly Gray, John Vienna, Patricia Paviet

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A001, July 22–26, 2018

Paper No: ICONE26-81017

DOI: https://doi.org/10.1115/ICONE26-81017

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Topics: Alloys, Ceramics, Composite materials, Cycles, Durability, Energy generation, Fast neutron reactors, Fuels, Glass, Glass ceramics

Proceedings Papers

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018

Paper No: ICONE26-81694

DOI: https://doi.org/10.1115/ICONE26-81694

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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams

Proceedings Papers

Preliminary Hazard Analysis of Uranium Hexafluoride Accident

Chen Lei, Zhang JianGang, Li GuoQiang, Sun ShuTang, Meng DongYuan, Wang Ning

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A030, July 22–26, 2018

Paper No: ICONE26-81956

DOI: https://doi.org/10.1115/ICONE26-81956

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Topics: Accidents, Hazard analysis, Uranium, Risk, Emergencies, Hazards, Nuclear fuel cycle

NARROW

Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Modelica Based Economic Analysis of Nuclear Fuel Cycle

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method

Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR

A Beyond Design Basis Earthquake Study of Operating Nuclear Fuel Cycle Facilities

The Safety of Nuclear Fuel Cycle Facilities in China After the Fukushima Accident

Thermal-Hydraulic Design Support and Safety Analyses of SEALER UK Demo

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

Experimental Setup for Non-Contact Displacement Measurement of Nuclear Waste via Electromagnetic Waves

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor

Overview of the U.S. Department of Energy Advanced Waste Forms Development

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Preliminary Hazard Analysis of Uranium Hexafluoride Accident

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