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Application of POD reduced-order algorithm on data-driven modeling of rod bundle

Nuclear Engineering and Technology, 2022, 54(1), , pp.36-48

2022

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Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles

Nuclear Engineering and Technology, 2022, 54(5), , pp.1825-1834

2022

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Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core

Nuclear engineering and technology, 2021-10, Vol.53 (10), p.3171-3181

2021

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Numerical Investigation of the Effect of Grids and Turbulence Models on Critical Heat Flux in a Vertical Pipe

Frontiers in energy research, 2018-07, Vol.6

2018

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Challenge Analysis and Schemes Design for the CFD Simulation of PWR

Science and Technology of Nuclear Installations, 2017-01, Vol.2017, p.1-15

2017

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Dynamic exergy analysis of feed water heater in nuclear power plant during start-up process

Energy (Oxford), 2024-04, Vol.292, p.130499, Article 130499

2024

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Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code

Science and Technology of Nuclear Installations, 2017-01, Vol.2017, p.1-13

2017

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Numerical Simulation of Water Hammer in Pipeline System Using Efficient Wave Tracking Method

Water resources management, 2023-06, Vol.37 (8), p.3053-3068

2023

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Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm

Nuclear engineering and design, 2023-04, Vol.404, p.112198, Article 112198

2023

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Advanced CFD modeling of rod bundle channels with integrated porous media and momentum source schemes

International communications in heat and mass transfer, 2024-06, Vol.155, p.107547, Article 107547

2024

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Uncertainty analysis and visualization for a coupled thermohydraulics-neutronics simulation by deterministic sampling

Journal of physics. Conference series, 2022-07, Vol.2313 (1), p.12006

2022

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Calculation of two-fluid subchannels model of pressurized water reactor: Picard Krylov method

International communications in heat and mass transfer, 2024-04, Vol.153, p.107356, Article 107356

2024

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Numerical study of uranium hexafluoride desublimation process based on Eulerian two-phase model

Heat transfer engineering, 2024-07, p.1-15

2024

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An advanced probability safety margin analysis approach combined deterministic and probabilistic safety assessment

Nuclear engineering and design, 2021-12, Vol.385, p.111514, Article 111514

2021

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Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles

Nuclear engineering and technology, 2022, Vol.54 (5), p.1825-1834

2022

Volltextzugriff (PDF)

Application of POD reduced-order algorithm on data-driven modeling of rod bundle

Nuclear engineering and technology, 2022, Vol.54 (1), p.36-48

2022

Volltextzugriff (PDF)

Distributed-parallel CFD computation for all fuel assemblies in PWR core

Annals of nuclear energy, 2020-06, Vol.141, p.107340, Article 107340

2020

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Investigating on multi-RANS models coupling simulation for flow mixing experiments

Annals of nuclear energy, 2020-07, Vol.142, p.107389, Article 107389

2020

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CFD simulation for the optimal design and utilization of experiment to research the flow process in PWR

Annals of nuclear energy, 2016-08, Vol.94, p.1-9

2016

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Numerical investigation of azimuthal heat conduction effects on CHF phenomenon in rod bundle channel

Annals of nuclear energy, 2018-11, Vol.121, p.203-209

2018

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Design and analysis of RIF scheme to improve the CFD effi ciency of rod-type PWR core

Nuclear Engineering and Technology, 2021, 53(10), , pp.3171-3181

2021

Volltextzugriff (PDF)

Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core

Nuclear engineering and technology, 2021, Vol.53 (10), p.3171-3181

2021

Volltextzugriff (PDF)

Design of a CFD scheme using multiple RANS models for PWR

Annals of nuclear energy, 2017-04, Vol.102, p.349-358

2017

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Research on the Subchannel Analysis Method via CFD Analysis for PWR

Nuclear science and engineering, 2017-12, Vol.188 (3), p.270-281

2017

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Numerical Investigation of Single-Phase Heat Transfer in a 2 × 2 Rod Bundle with Spacer Grids for a High Pressure Heat Transfer Facility

Nuclear technology, 2017-08, Vol.199 (2), p.174-186

2017

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Application of POD reduced-order algorithm on data-driven modeling of rod bundle

Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles

Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core

Numerical Investigation of the Effect of Grids and Turbulence Models on Critical Heat Flux in a Vertical Pipe

Challenge Analysis and Schemes Design for the CFD Simulation of PWR

Dynamic exergy analysis of feed water heater in nuclear power plant during start-up process

Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code

Numerical Simulation of Water Hammer in Pipeline System Using Efficient Wave Tracking Method

Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm

Advanced CFD modeling of rod bundle channels with integrated porous media and momentum source schemes

Uncertainty analysis and visualization for a coupled thermohydraulics-neutronics simulation by deterministic sampling

Calculation of two-fluid subchannels model of pressurized water reactor: Picard Krylov method

Numerical study of uranium hexafluoride desublimation process based on Eulerian two-phase model

An advanced probability safety margin analysis approach combined deterministic and probabilistic safety assessment

Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles

Application of POD reduced-order algorithm on data-driven modeling of rod bundle

Distributed-parallel CFD computation for all fuel assemblies in PWR core

Investigating on multi-RANS models coupling simulation for flow mixing experiments

CFD simulation for the optimal design and utilization of experiment to research the flow process in PWR

Numerical investigation of azimuthal heat conduction effects on CHF phenomenon in rod bundle channel

Design and analysis of RIF scheme to improve the CFD effi ciency of rod-type PWR core

Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core

Design of a CFD scheme using multiple RANS models for PWR

Research on the Subchannel Analysis Method via CFD Analysis for PWR

Numerical Investigation of Single-Phase Heat Transfer in a 2 × 2 Rod Bundle with Spacer Grids for a High Pressure Heat Transfer Facility

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