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Advancing fluid dynamics simulations: A comprehensive approach to optimizing physics-informed neural networks

Physics of fluids (1994), 2024-01, Vol.36 (1)

2024

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Self-adaptive and time divide-and-conquer physics-informed neural networks for two-phase flow simulations using interface tracking methods

Physics of fluids (1994), 2024-07, Vol.36 (7)

2024

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Robust bubble feature extraction in gas-liquid two-phase flow using object detection technique

Journal of nuclear science and technology, 2020-11, Vol.57 (11), p.1231-1244

2020

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Drift-flux modeling of void fraction for boiling two-phase flow in a tight-lattice rod bundle

International journal of heat and mass transfer, 2021-12, Vol.180, p.121769, Article 121769

2021

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Pressure Elevation of High-Performance Steam-Water Condensing-Injector

International journal of heat and mass transfer, 2021-05, Vol.170, p.120971, Article 120971

2021

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Experimental study of internal two-phase flow induced fluctuating force on a 90° elbow

Chemical engineering science, 2012-07, Vol.76, p.173-187

2012

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Research activities on nuclear reactor physics and thermal-hydraulics in Japan after Fukushima-Daiichi accident

Journal of nuclear science and technology, 2018-06, Vol.55 (6), p.575-598

2018

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Constitutive equations for vertical upward two-phase flow in rod bundle

International journal of heat and mass transfer, 2018-12, Vol.127, p.1252-1266

2018

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An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network

Nuclear Engineering and Technology, 2023, 55(9), , pp.3150-3163

2023

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A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics

Nuclear engineering and design, 2022-12, Vol.399, p.112029, Article 112029

2022

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Application of steam injector to improved safety of light water reactors

Progress in nuclear energy (New series), 2015-01, Vol.78, p.80-100

2015

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Investigation of the thermal-hydraulic characteristics of supersonic steam injector

Applied thermal engineering, 2016-10, Vol.109, p.261-271

2016

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Dimensionless parameters controlling the spreading behaviors of free-falling molten metal on dry surface

Progress in nuclear energy (New series), 2021-10, Vol.140, p.103882, Article 103882

2021

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Scaling analysis of the spreading and deposition behaviors of molten-core-simulated metals

Annals of nuclear energy, 2017-10, Vol.108, p.79-88

2017

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Inverted annular two-phase flow in multiphase flow systems

International journal of heat and mass transfer, 2022-05, Vol.186, p.122340, Article 122340

2022

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Local measurements of upward air-water two-phase flows in a vertical 6×6 rod bundle

Experimental and computational multiphase flow, 2019-09, Vol.1 (3), p.186-200

2019

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Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow

Progress in nuclear energy (New series), 2018-09, Vol.108, p.503-516

2018

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Evaluation of the in-vessel heat transfer for the debris removal of the Fukushima Daiichi nuclear power plant

Progress in nuclear energy (New series), 2020-01, Vol.119, p.103185, Article 103185

2020

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Image-Based Gas-Liquid Two-Phase Flow Analysis and Feature Extraction using Deep Learning

Journal of the Visualization Society of Japan, 2022, Vol.42(163), pp.19-22

MIWA, Shuichiro

2022

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Two-phase flow induced vibration in piping systems

Progress in nuclear energy (New series), 2015-01, Vol.78, p.270-284

2015

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Performance of drift-flux correlations for predicting void fraction of two-phase flow in tight-lattice rod bundles

International journal of heat and mass transfer, 2022-08, Vol.191, p.122664, Article 122664

2022

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Hydrodynamic Characterization of Nickel Metal Foam, Part 1: Single-Phase Permeability

Transport in porous media, 2009-11, Vol.80 (2), p.269-279

2009

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Comparison of Japanese and American Universities (Hokudai vs. Purdue): 日米大学・大学院比較 (北海道大学 vs. Purdue大学)

Journal of the Atomic Energy Society of Japan, 2019, Vol.61 (7), p.558-561

Miwa, Shuichiro

2019

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Comparison of Japanese and American Universities (Hokudai vs. Purdue)

Journal of the Atomic Energy Society of Japan, 2019, Vol.61(7), pp.558-561

Miwa, Shuichiro

2019

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Japanese T-H: A Small Step Towards Giant Leap

Journal of the Atomic Energy Society of Japan, 2019, Vol.61(4), pp.273-275

Miwa, Shuichiro

2019

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Advancing fluid dynamics simulations: A comprehensive approach to optimizing physics-informed neural networks

Self-adaptive and time divide-and-conquer physics-informed neural networks for two-phase flow simulations using interface tracking methods

Robust bubble feature extraction in gas-liquid two-phase flow using object detection technique

Drift-flux modeling of void fraction for boiling two-phase flow in a tight-lattice rod bundle

Pressure Elevation of High-Performance Steam-Water Condensing-Injector

Experimental study of internal two-phase flow induced fluctuating force on a 90° elbow

Research activities on nuclear reactor physics and thermal-hydraulics in Japan after Fukushima-Daiichi accident

Constitutive equations for vertical upward two-phase flow in rod bundle

An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network

A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics

Application of steam injector to improved safety of light water reactors

Investigation of the thermal-hydraulic characteristics of supersonic steam injector

Dimensionless parameters controlling the spreading behaviors of free-falling molten metal on dry surface

Scaling analysis of the spreading and deposition behaviors of molten-core-simulated metals

Inverted annular two-phase flow in multiphase flow systems

Local measurements of upward air-water two-phase flows in a vertical 6×6 rod bundle

Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow

Evaluation of the in-vessel heat transfer for the debris removal of the Fukushima Daiichi nuclear power plant

Image-Based Gas-Liquid Two-Phase Flow Analysis and Feature Extraction using Deep Learning

Two-phase flow induced vibration in piping systems

Performance of drift-flux correlations for predicting void fraction of two-phase flow in tight-lattice rod bundles

Hydrodynamic Characterization of Nickel Metal Foam, Part 1: Single-Phase Permeability

Comparison of Japanese and American Universities (Hokudai vs. Purdue): 日米大学・大学院比較 (北海道大学 vs. Purdue大学)

Comparison of Japanese and American Universities (Hokudai vs. Purdue)

Japanese T-H: A Small Step Towards Giant Leap

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