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Proceedings Papers

Study on Long-Life Minor Actinide Temporary Storage Scheme Based on High-Level Liquid Waste Partitioning Strategy

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Xiantao Meng, Meng Wei
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A043, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135666
https://doi.org/10.1115/ICONE31-135666
View Paper titled, Study on Long-Life Minor Actinide Temporary Storage Scheme Based on High-Level Liquid Waste Partitioning Strategy
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Topics: Storage
Proceedings Papers

Study on the Development Path of AFR Storage for Spent Fuel in China

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Lei Shi, Haoran Lu, Yihan Wang, Jian Hu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A051, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136022
https://doi.org/10.1115/ICONE31-136022
View Paper titled, Study on the Development Path of AFR Storage for Spent Fuel in China
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Topics: China, Construction, Spent nuclear fuels, Storage
Proceedings Papers

Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment

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Martin Lovecký, Jiří Závorka, Tomáš Kořínek, Radek Škoda
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A050, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136014
https://doi.org/10.1115/ICONE31-136014
View Paper titled, Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment
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Topics: Heat, Heavy water reactors, Light water reactors, Spent nuclear fuels, Uncertainty analysis
Proceedings Papers

Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed

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Chen Hao, Yu Chen Wen, Yi Zhen Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A033, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134979
https://doi.org/10.1115/ICONE31-134979
View Paper titled, Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed
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Topics: Geometry, Neutrons, Simulation, Stress, Very high temperature reactors
Proceedings Papers

Research on the ODR-VS Method Applicable to Various Geometric Models

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Zhiyuan Feng, Jingang Liang, Wenli Guo, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134943
https://doi.org/10.1115/ICONE31-134943
View Paper titled, Research on the ODR-VS Method Applicable to Various Geometric Models
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Topics: Ceramics, Cylinders, Discrete element methods, Ductility, Fuels, Geometric modeling, Metals, Modeling, Neutrons, Nuclear fuels
Proceedings Papers

Preliminary Investigation on Burst Behaviors of Zr-Based Cladding Under Simulated LOCA Conditions

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Zhengang Duan, Bo Yuan, Qinglong Wen, Kang Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134397
https://doi.org/10.1115/ICONE31-134397
View Paper titled, Preliminary Investigation on Burst Behaviors of Zr-Based Cladding Under Simulated LOCA Conditions
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Topics: Accidents, Cladding systems (Building), Fuels, Loss of coolant accidents, Zirconium
Proceedings Papers

Research on the Dependency Between Transuranic Isotopes and Burnup in Pebble Bed High-Temperature Reactors

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Zhang Hongjian, Zhu Qing, Zhang Liguo, Ma Tao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132764
https://doi.org/10.1115/ICONE31-132764
View Paper titled, Research on the Dependency Between Transuranic Isotopes and Burnup in Pebble Bed High-Temperature Reactors
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Topics: High temperature, Isotopes
Proceedings Papers

Thermal Cut-Off Energy for Accurate Analysis of Prismatic High-Temperature Gas-Cooled Reactor

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Satoshi Takeda, Takanori Kitada, Akio Yamamoto, Kazuya Yamaji, Hiroki Koike, Koji Asano
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130801
https://doi.org/10.1115/ICONE31-130801
View Paper titled, Thermal Cut-Off Energy for Accurate Analysis of Prismatic High-Temperature Gas-Cooled Reactor
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Topics: Very high temperature reactors
Proceedings Papers

Effect of Fission Products on Equilibrium U-Pu and Th-U Cycles for 16 Selected Reactors

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Josef Sabol, Francis Borys, Jiří Křepel
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A057, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136232
https://doi.org/10.1115/ICONE31-136232
View Paper titled, Effect of Fission Products on Equilibrium U-Pu and Th-U Cycles for 16 Selected Reactors
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Topics: Cycles, Equilibrium (Physics), Nuclear fission, Nuclear fuel cycle
Proceedings Papers

Comparison of EQL0D V2 and V4 Procedures by Means of Equilibrium U-Pu and Th-U Cycles in 16 Selected Reactors

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Jiří Křepel, Francis Borys, Josef Sabol, Evžen Losa
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A056, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136218
https://doi.org/10.1115/ICONE31-136218
View Paper titled, Comparison of EQL0D V2 and V4 Procedures by Means of Equilibrium U-Pu and Th-U Cycles in 16 Selected Reactors
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Topics: Cycles, Equilibrium (Physics), Nuclear fuel cycle
Proceedings Papers

Neutronic and Thermal-Hydraulic Analysis for Small Solid-Liquid Dual-Fuel Reactors With Different Fuel Elements

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Zhichao Qiu, Kun Zhuang, Yongzhan Wang, Xiaoyu Wang, Lina Deng, Yingzheng Wang, Sipeng Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A031, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134828
https://doi.org/10.1115/ICONE31-134828
View Paper titled, Neutronic and Thermal-Hydraulic Analysis for Small Solid-Liquid Dual-Fuel Reactors With Different Fuel Elements
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Topics: Fuels, Molten salt reactors
Proceedings Papers

Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor

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Jianhui Wu, Chunyan Zou, Chenggang Yu, Hongkai Zhao, Yong Cui, Haotian Bao, Xiangzhou Cai, Jingen Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134819
https://doi.org/10.1115/ICONE31-134819
View Paper titled, Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor
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Topics: Molten salt reactors, Nuclear fuel cycle, Safety, Temperature, Transients (Dynamics), Uranium
Proceedings Papers

Study on Neutronics Properties of Zirconium Hydride Moderator in Reactor

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Lin Shixin, Youqi Zheng
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A022, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134554
https://doi.org/10.1115/ICONE31-134554
View Paper titled, Study on Neutronics Properties of Zirconium Hydride Moderator in Reactor
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Topics: Metals, Zirconium
Proceedings Papers

Neutronics–Mechanics Coupling for Fast Transient Simulation in Molten Salt Reactors

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Théo Vidril, Stanislas de Lambert, Nicolas Lelong, Florence Drui, Cyril Patricot, Elsa Merle
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133060
https://doi.org/10.1115/ICONE31-133060
View Paper titled, Neutronics–Mechanics Coupling for Fast Transient Simulation in Molten Salt Reactors
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Topics: Molten salt reactors, Simulation, Transients (Dynamics)
Proceedings Papers

Method Research on the Model Optimization of Whole-Core Fuel-Assembly Bowing Based on 3D Variational Algorithm and the Measurement Values

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Lin Guo, Kai Zhang, Chenghui Wan, Hongchun Wu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A055, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136183
https://doi.org/10.1115/ICONE31-136183
View Paper titled, Method Research on the Model Optimization of Whole-Core Fuel-Assembly Bowing Based on 3D Variational Algorithm and the Measurement Values
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Topics: Algorithms, Fuels, Manufacturing, Optimization
Proceedings Papers

A Kind of Shielding Design and Verification Test of Radioactive Source Transport Container

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Lei Chen, ZhiPeng Wang, LiMing Jiao, DaJie Zhuang, Qian Sun, ChangWu Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136170
https://doi.org/10.1115/ICONE31-136170
View Paper titled, A Kind of Shielding Design and Verification Test of Radioactive Source Transport Container
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Topics: Containers, Design
Proceedings Papers

Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation

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Wen Yin, Tiejun Zu, Liangzhi Cao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135163
https://doi.org/10.1115/ICONE31-135163
View Paper titled, Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation
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Topics: Damage, Displacement, Electrons, Neutrons, Particulate matter
Proceedings Papers

Neutronics Research on Annular Axial-Non-Uniform Minor Actinides Transmutation Targets in Commercial Pressurized Water Reactor

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Bin Ye, Ayodeji A. Ala
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135114
https://doi.org/10.1115/ICONE31-135114
View Paper titled, Neutronics Research on Annular Axial-Non-Uniform Minor Actinides Transmutation Targets in Commercial Pressurized Water Reactor
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Topics: Pressurized water reactors
Proceedings Papers

Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor

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Yuxuan Wu, Yongping Wang, Shuai Qin, Liangzhi Cao, Hongchun Wu, Yong Luo
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A025, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134649
https://doi.org/10.1115/ICONE31-134649
View Paper titled, Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor
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Topics: Thermal hydraulics, Very high temperature reactors
Proceedings Papers

Hydrodynamics of High-Density Particles in a Multistage Fluidized Bed With Downcomers

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Yiming Zhang, Ying Yang, Huan Wang, Shuyue Li, Yongmin Zhang, Xiuhua Wu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133171
https://doi.org/10.1115/ICONE31-133171
View Paper titled, Hydrodynamics of High-Density Particles in a Multistage Fluidized Bed With Downcomers
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Topics: Density, Fluidized beds, Hydrodynamics, Particulate matter