专题：Nuclear Engineering Thermal-Hydraulics

This cluster of papers focuses on nuclear thermal hydraulics, particularly in the context of passive systems. It covers topics such as direct contact condensation, natural circulation loops, safety assessment, large eddy simulation, uncertainty evaluation, T-junction mixing, stability behavior, and reliability evaluation.
最新文献
Heterogeneous condensation reshapes relaxation, losses and efficiency in transonic condensing flows: an OpenFOAM-based moment-method study

article Full Text OpenAlex

Two phase flow instability of a natural circulation system with a narrow rectangular channel in floating nuclear power plants under rolling conditions

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Design and optimization of asymmetrical layouts in a printed circuit intermediate heat exchanger

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State-of-the-art and review of thermal-hydraulic and safety issues for lead-based fast reactors: experiment and numerical simulation

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Quantitative analysis of piping configuration effects on the hydraulic performance of the CAP1400 reactor coolant pump's core components via source term and modal decomposition methods

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Numerical study on heat transfer enhancement of LBE flow in semicircular-fin fuel bundles

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Thermal design of asymmetrical layout in printed circuit steam generators for molten salt-cooled high temperature reactor

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Inhibition of flow boiling instability for parallel microchannels using topological inlet restrictor at a reduced pressure drop

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Large language model-assisted digital twin for remote monitoring and control of advanced reactors

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A review of Monte Carlo-based multiphysics coupling in nuclear reactor analysis

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近5年高被引文献
A review of VOF methods for simulating bubble dynamics

article Full Text OpenAlex 176 FWCI17.4088

Redefined interface error, 2D verification and validation for pure solid-gallium phase change modeling by enthalpy-porosity methodology

article Full Text OpenAlex 160 FWCI15.762

Dynamic modeling and validation of the 5 MW small modular supercritical CO2 Brayton-Cycle reactor system

article Full Text OpenAlex 125 FWCI9.2133

Dynamic instabilities of flow boiling in micro-channels: A review

review Full Text OpenAlex 118 FWCI1.7415

Online autonomous calibration of digital twins using machine learning with application to nuclear power plants

article Full Text OpenAlex 115 FWCI9.411

Assessment of flow and heat transfer of triply periodic minimal surface based heat exchangers

article Full Text OpenAlex 97 FWCI9.4526

Heat transfer coefficient and pressure drop of water flow boiling in porous open microchannels heat sink

article Full Text OpenAlex 94 FWCI6.7936

Identification and Classification of the Flow Pattern of Hydrogen-Air-Steam Mixture Gas Under Steam Condensation

article Full Text OpenAlex 90 FWCI9.0758

Coupled Monte Carlo and thermal-fluid modeling of high temperature gas reactors using Cardinal

article Full Text OpenAlex 89 FWCI6.4206

Experimental evaluation on heat transfer limits of sodium heat pipe with screen mesh for nuclear reactor system

article Full Text OpenAlex 89 FWCI6.7006