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Proceedings Papers

Machine Learning Approach to Analyzing Data in Japanese BWR Chemistry Database

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Gaku Yamazaki
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134463
https://doi.org/10.1115/ICONE31-134463
View Paper titled, Machine Learning Approach to Analyzing Data in Japanese BWR Chemistry Database
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Topics: Boiling water reactors, Chemistry, Databases, Machine learning, Radiation (Physics)
Proceedings Papers

Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL

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Jingyu Nie, Binqian Li, Yingwei Wu, Jing Zhang, Guoliang Zhang, Qisen Ren, Yanan He, Guanghui Su
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A047, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135246
https://doi.org/10.1115/ICONE31-135246
View Paper titled, Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL
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Topics: Heat pipes, Simulation, Neutrons, Physics, Cross section (Physics), Databases, Density, Design, Modeling, Nuclear reactors
Proceedings Papers

Evaluation and Sensitivity Study of Uniform Kernel Method in Atmospheric 41 Ar Dispersion Against the Belgian Field Experiment

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Yeshuai Sun, Yujie Zhang, Zhaoyang Wang, Li Yang, Xinpeng Li, Yixue Chen, Xinwen Dong, Sheng Fang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A022, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135061
https://doi.org/10.1115/ICONE31-135061
View Paper titled, Evaluation and Sensitivity Study of Uniform Kernel Method in Atmospheric 41 Ar Dispersion Against the Belgian Field Experiment
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Topics: Contamination, Databases, Density, Emergency response, Engineering simulation, Meteorology, Nuclear power stations, Particulate matter, Radioisotopes, Sensitivity analysis
Proceedings Papers

Model Evaluation and Parallelization of Subchannel Analysis Code for Full-Core Pin-by-Pin Analysis

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Zhonghao Yu, Jinbiao Xiong
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133784
https://doi.org/10.1115/ICONE31-133784
View Paper titled, Model Evaluation and Parallelization of Subchannel Analysis Code for Full-Core Pin-by-Pin Analysis
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Topics: Databases, Errors, Flow (Dynamics), Friction, Modeling, Nuclear power plant operations, Nuclear reactors, Optimization, Pressurized water reactors, Resolution (Optics)
Proceedings Papers

Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level

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Mohammad Hashemi, Rafael Macián-Juan, Martin Ohlerich
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90636
https://doi.org/10.1115/ICONE29-90636
View Paper titled, Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level
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Topics: Manufacturing, Nuclear fission, Spent nuclear fuels, Chemical kinetics, Computer programming languages, Databases, Design, Nuclear power, Nuclear power stations, Parametric design
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
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

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

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Merouane Najar, He Wang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91516
https://doi.org/10.1115/ICONE29-91516
View Paper titled, Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW
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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors
Proceedings Papers

A New Correlation for Predictions of Heat Transfer of Lead-Bismuth Eutectic in Circular Tubes

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Zhengquan Wang, Qinglong Wen, Shijia Xu
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92378
https://doi.org/10.1115/ICONE29-92378
View Paper titled, A New Correlation for Predictions of Heat Transfer of Lead-Bismuth Eutectic in Circular Tubes
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Topics: Databases, Heat transfer
Proceedings Papers

Digital Twin-Driven Development of Online Monitoring and Data Management Systems in TMSR-SF0

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Wen-Qian Liu, Li-Feng Han, Li Huang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92770
https://doi.org/10.1115/ICONE29-92770
View Paper titled, Digital Twin-Driven Development of Online Monitoring and Data Management Systems in TMSR-SF0
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Topics: Data collection, Data storage systems, Databases, Design, Digital twin, Engines, Fuels, Industrial controls, Modeling, Molten salt reactors
Proceedings Papers

Construction of the Failed Fuel Information Database Platform

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Xin Liu, Changzheng Li, Yang Wang, Hongyang Zhang, Yongjun Deng
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93281
https://doi.org/10.1115/ICONE29-93281
View Paper titled, Construction of the Failed Fuel Information Database Platform
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Topics: Construction, Databases, Fuels, Manufacturing
Proceedings Papers

Development and Application of Nuclear Power Plant Life Cycle Management Database Platform

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Cao Guochang, Liu Zhao, Lv Fangming, Yang Zhenzhong, Jilang He, Cui Yixin
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A063, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93061
https://doi.org/10.1115/ICONE29-93061
View Paper titled, Development and Application of Nuclear Power Plant Life Cycle Management Database Platform
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Topics: Databases, Failure, Life cycle management, Nuclear power stations
Proceedings Papers

Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment

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Li Yang, Xinpeng Li, Yixue Chen, Boxin Wang, Sheng Fang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90806
https://doi.org/10.1115/ICONE29-90806
View Paper titled, Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment
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Topics: Interpolation, Optimization, Computational methods, Databases, Emergencies
Proceedings Papers

Experimental and Numerical Investigation on Debris Bed Quenching With Additional Injection of Non-Condensable Gas

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Markus Petroff, Rudi Kulenovic, Jörg Starflinger
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A031, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65512
https://doi.org/10.1115/ICONE28-65512
View Paper titled, Experimental and Numerical Investigation on Debris Bed Quenching With Additional Injection of Non-Condensable Gas
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Topics: Quenching (Metalworking), Particulate matter, Accidents, Cavities, Computer simulation, Concretes, Databases, Flow (Dynamics), Gases, Light water reactors
Proceedings Papers

Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases

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Eishiro Higo, Shota Soga, Hiromichi Miura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A010, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16819
https://doi.org/10.1115/ICONE2020-16819
View Paper titled, Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases
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Topics: Failure, Failure analysis, Databases, Probability, Nuclear power stations, Performance, Probabilistic risk assessment
Proceedings Papers

Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident

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Linyu Lin, Paridhi Athe, Pascal Rouxelin, Nam Dinh, Jeffrey Lane
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A033, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16908
https://doi.org/10.1115/ICONE2020-16908
View Paper titled, Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident
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Topics: Accidents, Control systems, Flow (Dynamics), Workflow, Databases, Safety, Breeder reactors, Decision making, Design, Engines
Proceedings Papers

Development and Assessment of Data-Driven Digital Twins in a Nearly Autonomous Management and Control System for Advanced Reactors

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Linyu Lin, Pascal Rouxelin, Paridhi Athe, Nam Dinh, Jeffrey Lane
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A027, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16813
https://doi.org/10.1115/ICONE2020-16813
View Paper titled, Development and Assessment of Data-Driven Digital Twins in a Nearly Autonomous Management and Control System for Advanced Reactors
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Topics: Control systems, Uncertainty, Databases, Flow (Dynamics), Modeling, Acceptance criteria, Accidents, Artificial neural networks, Design, Errors
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

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Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

First Attempt to Determine a Critical Heat Flux Correlation for Thermalhydraulic System Codes

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Christophe Herer, Antoine Lejosne
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A057, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81589
https://doi.org/10.1115/ICONE26-81589
View Paper titled, First Attempt to Determine a Critical Heat Flux Correlation for Thermalhydraulic System Codes
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Topics: Critical heat flux, Boiling, Fluids, Temperature, Vapors, Nucleate boiling, Uncertainty, Accidents, Cooling, Databases
Proceedings Papers

Development of a Thermal-Hydraulic Analysis Code for Helical Coiled Once Through Steam Generator

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Jun Huang, Junli Gou, Haifu Ma, Jie Fan, Jianqiang Shan
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81945
https://doi.org/10.1115/ICONE26-81945
View Paper titled, Development of a Thermal-Hydraulic Analysis Code for Helical Coiled Once Through Steam Generator
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Topics: Boilers, Heat transfer, Computers, Databases, Fluids, Heat exchangers, Nuclear power stations, Pressurized water reactors
Proceedings Papers

ALFRED Steam Generator Assessment: Design and Pre-Test Analysis of HERO Experiment

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Pierdomenico Lorusso, Alessio Pesetti, Mariano Tarantino
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A006, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81824
https://doi.org/10.1115/ICONE26-81824
View Paper titled, ALFRED Steam Generator Assessment: Design and Pre-Test Analysis of HERO Experiment
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Topics: Boilers, Design, Water, Engineering simulation, High pressure (Physics), Safety, Separation (Technology), Simulation, Circuits, Coolants