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Proceedings Papers

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022
Paper No: ICONE29-91761
DOI: https://doi.org/10.1115/ICONE29-91761
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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat
Proceedings Papers

Research on Deposition Performance of Fine Particles of Heat Pipe in Small Reactor

Xiaofang Liu, Tao Zhou, Shang Mao, Dong Wei
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A002, August 8–12, 2022
Paper No: ICONE29-89180
DOI: https://doi.org/10.1115/ICONE29-89180
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Topics: Flow (Dynamics), Heat pipes, Particulate matter, Temperature
Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022
Paper No: ICONE29-92103
DOI: https://doi.org/10.1115/ICONE29-92103
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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results
Proceedings Papers

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

Li Jiang, Jianqiang Shan
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A038, August 8–12, 2022
Paper No: ICONE29-93217
DOI: https://doi.org/10.1115/ICONE29-93217
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Topics: Fuel rods, Pressurized water reactors, Turbulence, Two-phase flow, Critical heat flux, Axial flow, Convection, Fluids, Pipes, Temperature
Proceedings Papers

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Wang Kai, Ming Jia Zhou, Wei Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A037, August 8–12, 2022
Paper No: ICONE29-91242
DOI: https://doi.org/10.1115/ICONE29-91242
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Topics: Automatic control, Control systems, Cooling, Design, Heating, Heating and cooling, Nuclear power stations, Pressure, Simulation, Temperature
Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022
Paper No: ICONE29-91707
DOI: https://doi.org/10.1115/ICONE29-91707
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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry
Proceedings Papers

Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations

Junlin Fang, Qian Sun, Yu Ji, Zishen Ye, Jun Sun, Zhe Sui
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A105, August 8–12, 2022
Paper No: ICONE29-92925
DOI: https://doi.org/10.1115/ICONE29-92925
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Topics: Gas flow, Heat conduction, Heat transfer, Thermal radiation, Convection, Design, Fuel rods, Pressurized water reactors, Radiation (Physics), Sodium fast reactors
Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022
Paper No: ICONE29-92872
DOI: https://doi.org/10.1115/ICONE29-92872
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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)
Proceedings Papers

Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling

Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A044, August 8–12, 2022
Paper No: ICONE29-91437
DOI: https://doi.org/10.1115/ICONE29-91437
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Topics: Fuels, Heat transfer, Modeling, Physics, Process control, Computational fluid dynamics, Nuclear reactors, Simulation, Convection, Finite element analysis
Proceedings Papers

A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference

Ruicheng Zhong, Yugao Ma, Qingzhu Zhao, Jian Deng, Yu Liu, Shuhua Ding
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A085, August 8–12, 2022
Paper No: ICONE29-92202
DOI: https://doi.org/10.1115/ICONE29-92202
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Topics: Condensation, Evaporation, Flow (Dynamics), Heat pipes, Sodium, Temperature, Thermal resistance, Transients (Dynamics), Steady state, Heat transfer
Proceedings Papers

Preliminary Design and Neutronics Analysis for a Medium Temperature Heat Pipe Cooled Reactor

Sina Li, Binhuo Yan, Guojun Tang, Donghong Peng, Hongzhi Lu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A017, August 8–12, 2022
Paper No: ICONE29-89659
DOI: https://doi.org/10.1115/ICONE29-89659
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Topics: Design, Heat pipes, Safety, Temperature, Uranium
Proceedings Papers

Effect of Temperature and Potential on BCC-Fe Nanoindentation Process

Dexin Wang, Pandong Lin, Libin Sun, Zhipeng Cai
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A038, August 8–12, 2022
Paper No: ICONE29-91251
DOI: https://doi.org/10.1115/ICONE29-91251
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Topics: Dislocations, Iron, Molecular dynamics, Nanoindentation, Temperature
Proceedings Papers

Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor

Risako Nakashima, Akari Koike, Takaaki Sakai, Norihiro Doda, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A107, August 8–12, 2022
Paper No: ICONE29-93039
DOI: https://doi.org/10.1115/ICONE29-93039
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Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants
Proceedings Papers

Experimental Investigation on Natural Circulation Characteristics of Core Make-Up Tank Under Rolling Conditions

Shuguang Wang, Jinlei Zhang, Ya'ou Shen, Xiaobo Liu, Shuhua Ding, Yusheng Liu, Dongyang Li, Jilin Tang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A087, August 8–12, 2022
Paper No: ICONE29-92254
DOI: https://doi.org/10.1115/ICONE29-92254
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Topics: Emergencies, Flow (Dynamics), Nuclear engineering, Nuclear power stations, Safety, Temperature, Temperature gradient, Thermal stratification, Thermocouples, Vessels
Proceedings Papers

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Paper No: ICONE29-92642
DOI: https://doi.org/10.1115/ICONE29-92642
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Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods
Proceedings Papers

Validation of TULIP via ICSBEP Critical Benchmark

Wenjie Chen, Xianan Du, Youqi Zheng, Yongping Wang, Rong Wang, Hongchun Wu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A113, August 8–12, 2022
Paper No: ICONE29-93353
DOI: https://doi.org/10.1115/ICONE29-93353
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Topics: Computational physics, Cross section (Physics), Design, Doppler effect, Feedback, Manufacturing, Neutrons, Nuclear design, Nuclear engineering, Nuclear fission
Proceedings Papers

Anomalies Detection in Structures, System and Components for Supporting Nuclear Long Term Operation Program

Salvatore Angelo Cancemi, Rosa Lo Frano
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A110, August 8–12, 2022
Paper No: ICONE29-93193
DOI: https://doi.org/10.1115/ICONE29-93193
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Topics: Algorithms, Digital twin, Failure, Finite element analysis, Machine learning, Maintenance, Nuclear power stations, Nuclear reactors, Pipes, Pressure
Proceedings Papers

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022
Paper No: ICONE29-89165
DOI: https://doi.org/10.1115/ICONE29-89165
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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design
Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Paper No: ICONE29-93082
DOI: https://doi.org/10.1115/ICONE29-93082
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022
Paper No: ICONE29-93417
DOI: https://doi.org/10.1115/ICONE29-93417
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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis