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Proceedings Papers

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

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

Paper No: ICONE29-93061

DOI: https://doi.org/10.1115/ICONE29-93061

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Topics: Databases, Failure, Life cycle management, Nuclear power stations

Proceedings Papers

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

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

Paper No: ICONE29-90636

DOI: https://doi.org/10.1115/ICONE29-90636

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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

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

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

Merouane Najar, He Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022

Paper No: ICONE29-91516

DOI: https://doi.org/10.1115/ICONE29-91516

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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors

Proceedings Papers

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

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

Paper No: ICONE29-90806

DOI: https://doi.org/10.1115/ICONE29-90806

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Topics: Interpolation, Optimization, Computational methods, Databases, Emergencies

Proceedings Papers

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

Zhengquan Wang, Qinglong Wen, Shijia Xu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A004, August 8–12, 2022

Paper No: ICONE29-92378

DOI: https://doi.org/10.1115/ICONE29-92378

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Topics: Databases, Heat transfer

Proceedings Papers

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

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

Paper No: ICONE29-92770

DOI: https://doi.org/10.1115/ICONE29-92770

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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

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

Paper No: ICONE29-93281

DOI: https://doi.org/10.1115/ICONE29-93281

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Topics: Construction, Databases, Fuels, Manufacturing

Proceedings Papers

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

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

Paper No: ICONE28-65512

DOI: https://doi.org/10.1115/ICONE28-65512

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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

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

Paper No: ICONE2020-16819

DOI: https://doi.org/10.1115/ICONE2020-16819

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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

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

Paper No: ICONE2020-16908

DOI: https://doi.org/10.1115/ICONE2020-16908

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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

Linyu Lin, Pascal Rouxelin, Paridhi Athe, Nam Dinh, Jeffrey Lane

Paper No: ICONE2020-16813

DOI: https://doi.org/10.1115/ICONE2020-16813

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Topics: Control systems, Uncertainty, Databases, Flow (Dynamics), Modeling, Acceptance criteria, Accidents, Artificial neural networks, Design, Errors

Proceedings Papers

Validation of CTF Void Predictions Using the BFBT Database

Nathan W. Porter, Maria N. Avramova, Vincent A. Mousseau

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A059, July 22–26, 2018

Paper No: ICONE26-81869

DOI: https://doi.org/10.1115/ICONE26-81869

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Topics: Databases, Equilibrium (Physics), Geometry, Porosity, Boundary-value problems, Calibration, Design, Modeling, Oscillations, Steady state

Proceedings Papers

Modeling of Low and High Void Fraction Two-Phase Flow in a Vertical Pipe by Using the Two-Fluid Model

Shimo Yu, Xiao Yan, Junyi Zhang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A019, July 22–26, 2018

Paper No: ICONE26-81583

DOI: https://doi.org/10.1115/ICONE26-81583

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Topics: Fluids, Modeling, Pipes, Porosity, Two-phase flow, Bubbles, Computational fluid dynamics, Databases, Flow (Dynamics), Heat transfer

Proceedings Papers

Design of a Closely-Spaced Rod Bundle for a Reference Direct Numerical Simulation

Afaque Shams, Tomasz Kwiatkowski

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A002, July 22–26, 2018

Paper No: ICONE26-81049

DOI: https://doi.org/10.1115/ICONE26-81049

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Topics: Computer simulation, Design, Fuel rods, Flow (Dynamics), Computational fluid dynamics, Reynolds-averaged Navier–Stokes equations, Heat transfer, Computation, Databases, Fluids

Proceedings Papers

Real-Time Online Risk Monitoring and Management Method for Maintenance Optimization in Nuclear Power Plant

Anqi Xu, Zhijian Zhang, HuaZhi Zhang, Min Zhang, He Wang, Yingfei Ma, Sijuan Chen, Yan Wang, Gangyang Zheng

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A021, July 22–26, 2018

Paper No: ICONE26-82472

DOI: https://doi.org/10.1115/ICONE26-82472

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Topics: Maintenance, Nuclear power stations, Optimization, Risk monitoring, Risk, Risk assessment, Errors, Modeling, Computational methods, Control systems

Proceedings Papers

Research Concept of Decommissioning Knowledge Management for the Fugen NPP

Yasuyoshi Taruta, Satoshi Yanagihara, Yukihiro Iguchi, Koichi Kitamura, Masashi Tezuka, Yuya Koda

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A005, July 22–26, 2018

Paper No: ICONE26-81228

DOI: https://doi.org/10.1115/ICONE26-81228

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Topics: Knowledge management, Nuclear decommissioning, Nuclear power stations, Databases, Accidents, Nuclear power, Construction, Contamination, Decontamination, Design

Proceedings Papers

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

Christopher Bennett, Scott Adams, Nick Alexander

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A021, July 22–26, 2018

Paper No: ICONE26-82628

DOI: https://doi.org/10.1115/ICONE26-82628

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Topics: Architects, Boilers, Databases, Design, Dimensions, Engineering disciplines, Nuclear power stations, Nuclear reactors, Safety, Small modular reactors

Proceedings Papers

The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool

Upendra Rohatgi, James Dyrda, Nicolas Soppera

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A022, July 22–26, 2018

Paper No: ICONE26-82631

DOI: https://doi.org/10.1115/ICONE26-82631

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Topics: Databases, Hydraulic drive systems, Nuclear reactors, Relational databases, Boiling water reactors, Computational fluid dynamics, Gas cooled reactors, High temperature, Instrumentation, Liquid metals

Proceedings Papers

Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code

Alessio Pesetti, Mariano Tarantino, Nicola Forgione

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A028, July 22–26, 2018

Paper No: ICONE26-82503

DOI: https://doi.org/10.1115/ICONE26-82503

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Topics: Boilers, Numerical analysis, Rupture, Vessels, Pressure, Water, Coolants, Design, Flow (Dynamics), Liquid metals

NARROW

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

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

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

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

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

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

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

Construction of the Failed Fuel Information Database Platform

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

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

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

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

Validation of CTF Void Predictions Using the BFBT Database

Modeling of Low and High Void Fraction Two-Phase Flow in a Vertical Pipe by Using the Two-Fluid Model

Design of a Closely-Spaced Rod Bundle for a Reference Direct Numerical Simulation

Real-Time Online Risk Monitoring and Management Method for Maintenance Optimization in Nuclear Power Plant

Research Concept of Decommissioning Knowledge Management for the Fugen NPP

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool

Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code

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