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Proceedings Papers

Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant

Yuxin Guan, Jiguo Chen, Guodong Zhang, Xuqiu Ren

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A033, August 8–12, 2022

Paper No: ICONE29-92184

DOI: https://doi.org/10.1115/ICONE29-92184

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Topics: Ceramics, Coolants, Membranes, Nuclear power stations, Pressurized water reactors, Water

Proceedings Papers

Study on UC Phase Control of UC Ceramic Microspheres Prepared by Sol-Gel Method

Feng Wen, Bolong Guo, Mingyang Li, Jiachen Wang, Fan Zhang, Wei Liu, Wenkai Ma, Zhihua Liu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A049, August 8–12, 2022

Paper No: ICONE29-92188

DOI: https://doi.org/10.1115/ICONE29-92188

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Topics: Ceramics, Sol-gel processing

Proceedings Papers

Preparation and Properties of Ceramic Solidified Product Containing Cs and Sr

Hongji Sang, Zhengcheng Gu, Zheng Cui, Ruoxue Zou, Yan Wu

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A031, August 8–12, 2022

Paper No: ICONE29-92765

DOI: https://doi.org/10.1115/ICONE29-92765

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Topics: Ceramics, Solidification, Sintering, Crystallization, Half-life, Heat, Melting, Minerals, Radioactivity, Work hardening

Proceedings Papers

Structure Control of a HLW Immobilized Zirconolite Glass-Ceramic Matrix

Haiqing Li, Yutong Pan, Chao Gao, Shuming Wang

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A036, August 8–12, 2022

Paper No: ICONE29-93212

DOI: https://doi.org/10.1115/ICONE29-93212

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Topics: Ceramics, Glass, Glass ceramics, Crystallization, Temperature, Crystals, Durability, Heat treating (Metalworking), Nucleation (Physics), Nuclides

Proceedings Papers

Experimental Study on the Feasibility of Dry Grinding of MOX Core Blocks

Jianzhong Mao, Xin Liu, Ben Wang, Pengfei Zhang, Bo Gao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A033, August 8–12, 2022

Paper No: ICONE29-92415

DOI: https://doi.org/10.1115/ICONE29-92415

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Topics: Ceramics, Grinding, Temperature

Proceedings Papers

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

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang

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, V001T03A008, August 4–6, 2021

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

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Jin Feng Huang

Paper No: ICONE28-63314

DOI: https://doi.org/10.1115/ICONE28-63314

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Topics: Ceramics, Fuels, Pressurized water reactors, Cladding systems (Building), Cycles, Nuclear power stations, Silicon, Temperature, Thermal conductivity, Boron

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

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

Study on the Thermal-Mechanical Performance of SiC Composites Cladding Under Multiple Conditions

Chunyu Yin

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, V001T05A013, August 4–5, 2020

Paper No: ICONE2020-16793

DOI: https://doi.org/10.1115/ICONE2020-16793

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Topics: Cladding systems (Building), Composite materials, Failure, Hoop stress, Fracture toughness, Probability, Temperature, Accidents, Brittleness, Ceramics

Proceedings Papers

Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium

Liang Hu, Kui Ge, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A024, July 22–26, 2018

Paper No: ICONE26-81400

DOI: https://doi.org/10.1115/ICONE26-81400

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Topics: Sodium, Copper, Pressure, Sodium fast reactors, Accidents, Boiling, Ceramics, Compacting, Coolants, Cooling

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

Conceptual Design of the Water Cooled Breeder Blanket for Both Phases of CFETR

Songlin Liu, Xuebin Ma, Kecheng Jiang, Min Li, Xiaokang Zhang

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A016, July 22–26, 2018

Paper No: ICONE26-81816

DOI: https://doi.org/10.1115/ICONE26-81816

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Topics: Conceptual design, Water, Coolants, Design, Temperature, Neutrons, Plasmas (Ionized gases), Thermal hydraulics, Ceramics, Construction

Proceedings Papers

Preliminary Neutron Simulation of Ceramic Fast Reactor

Xuesong Yan, Xunchao Zhang, Yaling Zhang, Lei Yang, Wenshan Duan

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A021, July 22–26, 2018

Paper No: ICONE26-81474

DOI: https://doi.org/10.1115/ICONE26-81474

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Topics: Ceramics, Fast neutron reactors, Neutrons, Simulation, Absorption, Coolants, Energy generation, Nuclear fuels, Nuclear power, Nuclear reactors

Proceedings Papers

Comparison of Advanced Melting Process for HLW Vitrification, Joule-Heated Ceramic-Lined Melter (JHCM) and Cold-Crucible Induction Melter (CCIM)

Akira Sakai, Hajime Koikegami, Siegfried Weisenburger, Guenther Roth, Norio Kanehira, Satoshi Komamine

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A038, July 2–6, 2017

Paper No: ICONE25-67807

DOI: https://doi.org/10.1115/ICONE25-67807

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Topics: Ceramics, Electromagnetic induction, Joules, Melting, Vitrification, Glass, Metals, Spent nuclear fuels, Water, Borosilicate glasses

Proceedings Papers

Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly

Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A012, July 2–6, 2017

Paper No: ICONE25-66444

DOI: https://doi.org/10.1115/ICONE25-66444

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Topics: Fuels, Manufacturing, Pressurized water reactors, Boron, Cycles, Nuclear reactors, Safety, Accidents, High temperature, Ceramics

Proceedings Papers

Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method

Jikui Li, Liangzhi Cao, Tiejun Zu, HongChun Wu, Qingming He

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A030, July 2–6, 2017

Paper No: ICONE25-66810

DOI: https://doi.org/10.1115/ICONE25-66810

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Topics: Ceramics, Fuels, Resonance, Computational methods, Cross section (Physics), Modeling, Particulate matter

Proceedings Papers

New Exploration on TMSR: Redesign of the TMSR Lattice

Jinkun Zhao, Shengyi Si, Qichang Chen, Hua Bei

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A016, July 2–6, 2017

Paper No: ICONE25-66564

DOI: https://doi.org/10.1115/ICONE25-66564

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Topics: Breeder reactors, Ceramics, Cladding systems (Building), Coolants, Corrosion, Design, Fast neutron reactors, Flow (Dynamics), Fluids, Fuels

Proceedings Papers

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

Kun Xu, Minyou Ye, Yuntao Song, Mingzhun Lei, Shifeng Mao

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A035, July 2–6, 2017

Paper No: ICONE25-67291

DOI: https://doi.org/10.1115/ICONE25-67291

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Topics: Ceramics, Helium, Lithium, Design, China, Energy generation, Tokamaks, Vacuum, Vessels, Bridges (Structures)

Proceedings Papers

DEM-CFD Study of Purge Gas Flow in Pebble Bed of WCCB for CFETR

Youhua Chen, Lei Chen, Songlin Liu

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A005, July 2–6, 2017

Paper No: ICONE25-66211

DOI: https://doi.org/10.1115/ICONE25-66211

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Topics: Computational fluid dynamics, Discrete element methods, Gas flow, Packing (Shipments), Packings (Cushioning), Flow (Dynamics), Design, Pressure drop, Ceramics, China

NARROW

Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant

Study on UC Phase Control of UC Ceramic Microspheres Prepared by Sol-Gel Method

Preparation and Properties of Ceramic Solidified Product Containing Cs and Sr

Structure Control of a HLW Immobilized Zirconolite Glass-Ceramic Matrix

Experimental Study on the Feasibility of Dry Grinding of MOX Core Blocks

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

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR

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

Study on the Thermal-Mechanical Performance of SiC Composites Cladding Under Multiple Conditions

Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium

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

Conceptual Design of the Water Cooled Breeder Blanket for Both Phases of CFETR

Preliminary Neutron Simulation of Ceramic Fast Reactor

Comparison of Advanced Melting Process for HLW Vitrification, Joule-Heated Ceramic-Lined Melter (JHCM) and Cold-Crucible Induction Melter (CCIM)

Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly

Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method

New Exploration on TMSR: Redesign of the TMSR Lattice

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

DEM-CFD Study of Purge Gas Flow in Pebble Bed of WCCB for CFETR

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