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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

DOI: https://doi.org/10.1115/ICONE29-93103

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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

DOI: https://doi.org/10.1115/ICONE29-91399

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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

DOI: https://doi.org/10.1115/ICONE29-90510

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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

DOI: https://doi.org/10.1115/ICONE29-89241

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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

DOI: https://doi.org/10.1115/ICONE29-90902

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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

DOI: https://doi.org/10.1115/ICONE29-94480

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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

DOI: https://doi.org/10.1115/ICONE29-90217

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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

DOI: https://doi.org/10.1115/ICONE29-93201

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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors

Proceedings Papers

Development and Verification of Thermal-Hydraulic Constitutive Model for Rectangular Channel

Yun Fei Feng, Lei Li, Ya Jie Nie, Xin Jiao, Jian Yi Li, Si Jia Meng, Ying Hao Li

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A026, August 8–12, 2022

Paper No: ICONE29-92795

DOI: https://doi.org/10.1115/ICONE29-92795

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Topics: Accidents, Constitutive equations, Critical heat flux, Flow (Dynamics), Fuels, Heart failure, Heat transfer, Heat transfer coefficients, Low temperature, Nuclear reactors

Proceedings Papers

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Peng Yuan, Jian Deng, Zhifang Qiu, Qinglan Xu, Dahuan Zhu, Tao Huang, Zhongchun Li, Peng Du

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A006, August 8–12, 2022

Paper No: ICONE29-92380

DOI: https://doi.org/10.1115/ICONE29-92380

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Topics: Accidents, Algorithms, Artificial neural networks, China, Coolants, Design, Flow (Dynamics), Machine learning, Nuclear power stations, Nuclear reactors

Proceedings Papers

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Jinsong Guo, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, Yuhao Zhang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A003, August 8–12, 2022

Paper No: ICONE29-92364

DOI: https://doi.org/10.1115/ICONE29-92364

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Topics: Computer simulation, Heat, Modeling, Flow (Dynamics), Wire, Fuel rods, Porous materials, Safety, Sodium fast reactors, Dynamics (Mechanics)

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

DOI: https://doi.org/10.1115/ICONE29-91474

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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling

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

DOI: https://doi.org/10.1115/ICONE29-91692

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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

DOI: https://doi.org/10.1115/ICONE29-89017

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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

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

Xiaoyan Yang, Hongyi Yang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A072, August 8–12, 2022

Paper No: ICONE29-92214

DOI: https://doi.org/10.1115/ICONE29-92214

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Topics: Kalman filters, Design, Nuclear reactors, Porosity, Safety, Simulation, Transients (Dynamics)

Proceedings Papers

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022

Paper No: ICONE29-89568

DOI: https://doi.org/10.1115/ICONE29-89568

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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability

Proceedings Papers

Development of Quench Analysis Program Based on ARSAC

Lei Zhong, Hongxing Yu, Deqi Chen, Hanzhou Liu, Jian Deng, Dan Wu

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A062, August 8–12, 2022

Paper No: ICONE29-92080

DOI: https://doi.org/10.1115/ICONE29-92080

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Topics: Boiling, China, Cladding systems (Building), Film boiling, Fuels, Heat transfer, Nuclear reactors, Oxidation, Quenching (Metalworking), Temperature

Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022

Paper No: ICONE29-89917

DOI: https://doi.org/10.1115/ICONE29-89917

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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission

Proceedings Papers

Measurement of Two-Phase Flow: Static CT System Based on Carbon Nanotubes

Yucheng Zhang, Shuo Xu, Xincheng Xiang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A012, August 8–12, 2022

Paper No: ICONE29-92492

DOI: https://doi.org/10.1115/ICONE29-92492

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Topics: Carbon nanotubes, Porosity, Two-phase flow, Flow (Dynamics), X-rays, Imaging, Sensors, Bubbles, Computers, Density

Proceedings Papers

Research on the Natural Circulation Flow in Deep Pool-Type Nuclear Reactor

Gongqing Wang, Zhiting Yue, Rulei Sun, Bo Wang, Xingmin Liu, Ruifeng Tian

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A069, August 8–12, 2022

Paper No: ICONE29-92183

DOI: https://doi.org/10.1115/ICONE29-92183

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Topics: Flow (Dynamics), Nuclear reactors

2 3 4 5

NARROW

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

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

Molten Salt Reactor Experiment Simulation Using ThorMOC

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

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

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

TCR Central Shutdown Rod Fine Motion Control

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

Development and Verification of Thermal-Hydraulic Constitutive Model for Rectangular Channel

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

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

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

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

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Development of Quench Analysis Program Based on ARSAC

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Measurement of Two-Phase Flow: Static CT System Based on Carbon Nanotubes

Research on the Natural Circulation Flow in Deep Pool-Type Nuclear Reactor

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