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Proceedings Papers

Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC

Pengfei Shen, Jingang Liang, Shichang Liu, Kan Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A075, August 8–12, 2022
Paper No: ICONE29-93103
https://doi.org/10.1115/ICONE29-93103
View Paper titled, Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC
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Topics: Computer-aided design, Engineering simulation, Geometry, Nuclear reactors, Particulate matter, Physics, Simulation, Transport processes, Weight (Mass)
Proceedings Papers

Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP

Kui Hu, Xubo Ma, Xuan Ma, Chen Zhang, Guanqun Jia, Yixue Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A031, August 8–12, 2022
Paper No: ICONE29-91399
https://doi.org/10.1115/ICONE29-91399
View Paper titled, Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP
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Topics: Approximation, Cross section (Physics), Errors, Intellectual property, Neutrons, Nuclear reactors, Nuclides, Physics
Proceedings Papers

Molten Salt Reactor Experiment Simulation Using ThorMOC

Ao Zhang, Ming Dai, Maosong Cheng, Jingen Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A014, August 8–12, 2022
Paper No: ICONE29-90510
https://doi.org/10.1115/ICONE29-90510
View Paper titled, Molten Salt Reactor Experiment Simulation Using ThorMOC
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Topics: Molten salt reactors, Simulation, Modeling, Eigenvalues, Graphics processing units, Neutrons, Nuclear reactors
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

Rui Li, Shichang Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 8–12, 2022
Paper No: ICONE29-90902
https://doi.org/10.1115/ICONE29-90902
View Paper titled, Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
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Topics: Nuclear reactors, Nuclides, Radiation (Physics), Neutrons, Cross section (Physics), Monte Carlo methods, Photons, Absorption, Databases, Elastic scattering
Proceedings Papers

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Jun Liao, Alexander Mace, Guoqiang Wang, Jesse S. Fisher
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A095, August 8–12, 2022
Paper No: ICONE29-94480
https://doi.org/10.1115/ICONE29-94480
View Paper titled, Applying Machine Learning to Improve BOA Analysis of CIPS/CILC
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Topics: Machine learning, Boron, Corrosion, Fuels, Nuclear power stations, Algorithms, Calibration, Chemistry, Cladding systems (Building), Computers
Proceedings Papers

TCR Central Shutdown Rod Fine Motion Control

Venugopal K. Varma, Eliott Fountain, Earle Burkhardt, Sacit Cetiner, Dustin Ottinger
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A009, August 8–12, 2022
Paper No: ICONE29-90217
https://doi.org/10.1115/ICONE29-90217
View Paper titled, TCR Central Shutdown Rod Fine Motion Control
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Topics: Electromagnets, Motion control, Design, Pressure vessels, Actuators, Artificial intelligence, Engineering prototypes, Engines, Gravity (Force), Helium
Proceedings Papers

Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR

Yanfei Qiu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A033, August 8–12, 2022
Paper No: ICONE29-93201
https://doi.org/10.1115/ICONE29-93201
View Paper titled, Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR
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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors
Proceedings Papers

Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition

Kun Cheng, Xiao Chu, Zhifang Qiu, Lin Xian, Jian Deng
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A023, August 8–12, 2022
Paper No: ICONE29-92063
https://doi.org/10.1115/ICONE29-92063
View Paper titled, Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition
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Topics: Nuclear reactors, Oceans
Proceedings Papers

The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102

Yijie Qian, Chong Li
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A026, August 8–12, 2022
Paper No: ICONE29-91692
https://doi.org/10.1115/ICONE29-91692
View Paper titled, The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102
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Topics: China, Fusion reactors, Safety, Design, Defense industry, Nuclear design, Nuclear fission, Nuclear fusion, Nuclear reactors, Regulations
Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis
Proceedings Papers

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Yifeng Hu, Zhiqiang Hu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A013, August 8–12, 2022
Paper No: ICONE29-91474
https://doi.org/10.1115/ICONE29-91474
View Paper titled, Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines
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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling
Proceedings Papers

Research on LOCA Dynamic Analysis Model of Reactor System

Shuai Liu
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A023, August 8–12, 2022
Paper No: ICONE29-92491
https://doi.org/10.1115/ICONE29-92491
View Paper titled, Research on LOCA Dynamic Analysis Model of Reactor System
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Topics: Dynamic analysis, Nuclear reactors
Proceedings Papers

A Knowledge Retrieval Method for Layout Design of Nuclear Power Reactor Coolant System Based on Hypernetwork and Deep Structured Semantic Model

Bin Wang, Bingtao Hu, Zhifeng Zhang, Yixiong Feng, Jianrong Tan
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A010, August 8–12, 2022
Paper No: ICONE29-91827
https://doi.org/10.1115/ICONE29-91827
View Paper titled, A Knowledge Retrieval Method for Layout Design of Nuclear Power Reactor Coolant System Based on Hypernetwork and Deep Structured Semantic Model
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Topics: Coolants, Design, Nuclear reactors, Semantics
Proceedings Papers

Research on Accident Diagnosis Method of Reactor System Based on XGBoost Using Bayesian Optimization

Yongchao Liu, Xiangyu Li, Biao Liang, Bo Wang, Sichao Tan, Puzhen Gao
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A015, August 8–12, 2022
Paper No: ICONE29-92061
https://doi.org/10.1115/ICONE29-92061
View Paper titled, Research on Accident Diagnosis Method of Reactor System Based on XGBoost Using Bayesian Optimization
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Topics: Accidents, Nuclear reactors, Optimization
Proceedings Papers

The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor

Fangyu Dong, Jinyan Du, Chao Ma, Wei Deng, Qingqing Xu, Rui Zhang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A019, August 8–12, 2022
Paper No: ICONE29-91663
https://doi.org/10.1115/ICONE29-91663
View Paper titled, The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor
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Topics: Heat, Nuclear reactors, Probabilistic safety assessment, Risk, Risk monitoring, Risk management, Design, Nuclear power stations, Decision making, Maintenance
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
https://doi.org/10.1115/ICONE29-92925
View Paper titled, Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations
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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

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
https://doi.org/10.1115/ICONE29-91437
View Paper titled, Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling
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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
https://doi.org/10.1115/ICONE29-92202
View Paper titled, A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference
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Topics: Condensation, Evaporation, Flow (Dynamics), Heat pipes, Sodium, Temperature, Thermal resistance, Transients (Dynamics), Steady state, Heat transfer
Proceedings Papers

Reactivity Introduction Accident and Control Strategy Analysis of Small Modular Supercritical CO2 Brayton-Cycle Reactor System

Yang Ming, Yang Jin, Yanlong Qiao, Fulong Zhao, Ruifeng Tian
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A080, August 8–12, 2022
Paper No: ICONE29-92122
https://doi.org/10.1115/ICONE29-92122
View Paper titled, Reactivity Introduction Accident and Control Strategy Analysis of Small Modular Supercritical CO2 Brayton-Cycle Reactor System
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Topics: Accidents, Brayton cycle, Nuclear reactors, Supercritical carbon dioxide