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Proceedings Papers

Analysis of the Effect of Random Bowing of the Fuel Pin on the Power Distribution in the Fuel Assembly

Jiří Závorka, Martin Lovecký, Radek Škoda, Petra Monhartová
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A059, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136287
https://doi.org/10.1115/ICONE31-136287
View Paper titled, Analysis of the Effect of Random Bowing of the Fuel Pin on the Power Distribution in the Fuel Assembly
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Topics: Fuels, Manufacturing
Proceedings Papers

Analysis on Permeation Leakage Through Rubber Sealing Ring for Radioactive Material Transport Packages

Pengyi Wang, Dajie Zhuang, Hongchao Sun, Lei Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136263
https://doi.org/10.1115/ICONE31-136263
View Paper titled, Analysis on Permeation Leakage Through Rubber Sealing Ring for Radioactive Material Transport Packages
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Topics: Helium, Leakage, Radioactive substances, Rubber, Sealing (Process), Testing, Transport packages
Proceedings Papers

Investigation on Applicability of Dynamic Mode Decomposition in Burnup Analysis

Pengchao Xue, Qian Zhang, Qiang Zhao, Yunfei Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135535
https://doi.org/10.1115/ICONE31-135535
View Paper titled, Investigation on Applicability of Dynamic Mode Decomposition in Burnup Analysis
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Topics: Algorithms, Density, Dynamics (Mechanics), Fuels, Manufacturing, Neutrons, Nuclides, Spatiotemporal phenomena
Proceedings Papers

Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis

Yuancheng Zhou, Yunzhao Li, Yisong Li, Yilin Liang, Hengrui Zhang, Shilong Zhou, Weiguo Wang, Yuxiang Ou
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A038, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135358
https://doi.org/10.1115/ICONE31-135358
View Paper titled, Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis
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Topics: Modeling, Physics, Pressurized water reactors
Proceedings Papers

Effect of Heat Treatment on Microstructure Characteristics of Hot Worked Zr-2.5Nb Alloy Tubes

Jianming Yin, Bo Gao, Baifeng Luan, Yan Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134410
https://doi.org/10.1115/ICONE31-134410
View Paper titled, Effect of Heat Treatment on Microstructure Characteristics of Hot Worked Zr-2.5Nb Alloy Tubes
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Topics: Alloys, Heat treating (Metalworking), Zirconium
Proceedings Papers

Further Study of China’s Strategy for Closed Nuclear Fuel Cycle Development Against the Carbon Neutrality Target

Ding Chen, Lei Shi, Jiqiang Su, Yan An, Yihan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133248
https://doi.org/10.1115/ICONE31-133248
View Paper titled, Further Study of China’s Strategy for Closed Nuclear Fuel Cycle Development Against the Carbon Neutrality Target
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Topics: Carbon neutrality, Nuclear fuel cycle
Proceedings Papers

Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method

Baoxin Yuan, Huiyi Lv, Herong Zeng, Jie Zheng, Zihan Chen, Huan Huang, Songbao Zhang, Dazhi Qian
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132052
https://doi.org/10.1115/ICONE31-132052
View Paper titled, Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method
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Topics: Damage, Failure, Finite element methods, Fuels, Neutrons, Noise (Sound)
Proceedings Papers

TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme

Junxiao Zhang, Songyang Liu, Junhao Xie, Tian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136107
https://doi.org/10.1115/ICONE31-136107
View Paper titled, TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme
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Topics: Fuels, High temperature, Particulate matter, Nuclear fission, Temperature, Very high temperature reactors, Diffusion (Physics), Failure, Flow (Dynamics), Safety
Proceedings Papers

Study on the Characteristics of Nuclear Fuel Industry

Lei Shi, Yihan Wang, Hongjun Liu, Honglin Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A052, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136048
https://doi.org/10.1115/ICONE31-136048
View Paper titled, Study on the Characteristics of Nuclear Fuel Industry
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Topics: Nuclear fuels
Proceedings Papers

Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel

Duan Qianni, Li Wei, Wu Junmei
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135085
https://doi.org/10.1115/ICONE31-135085
View Paper titled, Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel
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Topics: High cycle fatigue, Nuclear fuels, Neutrons, Physics, Power density, Fuels, Geometry, Innovation, Thermal hydraulics, Uranium
Proceedings Papers

A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors

Yue Song, Heng Xie, Meng Lv
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A034, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135005
https://doi.org/10.1115/ICONE31-135005
View Paper titled, A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors
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Topics: Corrosion, Fuels, Irradiation (Radiation exposure), Safety, Temperature effects
Proceedings Papers

High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM

Ruihan Li, Jingang Liang, Ding She, Weijian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134641
https://doi.org/10.1115/ICONE31-134641
View Paper titled, High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM
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Topics: Discrete element methods, Flow (Dynamics), Simulation
Proceedings Papers

Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent

Xingyu Zhao, Guodong Liu, Shanfang Huang, Qiaoyan Chen, Hao Luo, Ying He, Junren Hou, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133607
https://doi.org/10.1115/ICONE31-133607
View Paper titled, Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent
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Topics: Computational fluid dynamics, Geometry, Thermal hydraulics
Proceedings Papers

Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor

Satoshi Takeda, Takanori Kitada, Eiji Hoashi, Takafumi Okita
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132277
https://doi.org/10.1115/ICONE31-132277
View Paper titled, Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor
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Topics: Sodium fast reactors
Proceedings Papers

Fast Solution of Schrödinger Equation Based on Complex One-Dimensional Potential Wells

Zihao Liu, Xiang Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A067, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-137072
https://doi.org/10.1115/ICONE31-137072
View Paper titled, Fast Solution of Schrödinger Equation Based on Complex One-Dimensional Potential Wells
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Topics: Schrödinger equation, Wells
Proceedings Papers

Adsorption and Diffusion of Silver on SiC(111) and ZrC(111) Surfaces: A First Principles Study

Jiaxuan Li, Hongwei Zhu, Taowei Wang, Zelin Gao, Xiaotong Chen, Gang Xu, Bing Liu, Yaping Tang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A066, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-137055
https://doi.org/10.1115/ICONE31-137055
View Paper titled, Adsorption and Diffusion of Silver on SiC(111) and ZrC(111) Surfaces: A First Principles Study
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Topics: Diffusion (Physics), Silicon carbide, Silver
Proceedings Papers

Irradiation-Thermal-Mechanical Coupling Behaviors of a Typical TRISO/SiC Fuel Element Based on Actual Distribution

Zhang Liangjie, Chen Ping, Liu Shichao, Wang Haoyu, Wei Chong, Pan Xiaoqiang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135863
https://doi.org/10.1115/ICONE31-135863
View Paper titled, Irradiation-Thermal-Mechanical Coupling Behaviors of a Typical TRISO/SiC Fuel Element Based on Actual Distribution
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Topics: Finite element model, Fuels, Irradiation (Radiation exposure), Silicon carbide
Proceedings Papers

Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors

Changbing Tang, Yuanming Li, Haoyu Liao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A044, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135696
https://doi.org/10.1115/ICONE31-135696
View Paper titled, Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors
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Topics: Computer simulation, Failure, Fuels, Irradiation (Radiation exposure)
Proceedings Papers

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Shichang Liu, Zhenyu Wang, Rui Che
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134661
https://doi.org/10.1115/ICONE31-134661
View Paper titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
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Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Proceedings Papers

A Preconditioning Method Based on Strongly Implicit Procedure for the Multi- Diagonal Equation

Bo Tan, Haojie Zhang, Yutong Wen, Ding She
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133656
https://doi.org/10.1115/ICONE31-133656
View Paper titled, A Preconditioning Method Based on Strongly Implicit Procedure for the Multi- Diagonal Equation
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Topics: Algorithms, Convection, Cylinders, Diffusion (Physics), Heat conduction, Neutrons, Nuclear engineering, Numerical analysis, Partial differential equations, Physics