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Maolong Liu

fudan university

H指数:18

被引数:974

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Transient analysis of the safety characteristics on the lead-bismuth eutectic cooled fast reactor LFR-180

铅铋共晶冷却快堆LFR-180的安全特性瞬态分析

Progress in Nuclear Energy

IF3.2

2026-05-050

PRE

Effects of particle deposition on heat transfer and resistance characteristics of molten salt flow in helical coil tube bundles

螺旋线圈管束中熔盐流动的传热和阻力特性受颗粒沉积的影响

Applied Thermal Engineering

IF6.9

2026-04-020

PRE

Multiscale CFD-DEM investigation on deposition characteristics of metal particles in flowing molten salt

多尺度CFD-DEM对流动熔融盐中金属颗粒沉积特性的研究

International Communications in Heat and Mass Transfer

IF6.4

2025-11-040

PRE

Impact of deposition morphology on critical heat flux during pool boiling from horizontal tubes

沉积形态对水平管池沸腾过程中临界热通量的影响

ANNALS OF NUCLEAR ENERGY

IF2.3

2025-10-010

PRE

Numerical study of lead oxide precipitation in liquid lead-bismuth eutectic

液态铅铋共晶中氧化铅沉淀的数值研究

ANNALS OF NUCLEAR ENERGY

IF2.3

2025-09-010

PRE

Development of a new onset of nucleate boiling model for helical tubes

开发螺旋管核态沸腾新起始模型

INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER

IF6.4

2025-05-010

OAAI

Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators

PROGRESS IN NUCLEAR ENERGY

IF3.2

2025-05-010

PRE

Numerical safety analysis on a conceptual design of fluoride-salt-cooled high-temperature reactors under the influence of ocean conditions

PROGRESS IN NUCLEAR ENERGY

IF3.2

2025-02-010

PRE

Numerical study on flow instability in parallel helical tubes under ocean conditions

INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER

IF6.4

2024-12-010

PRE

Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids

具有间隔网格的棒束中近临界水的热工水力的数值研究

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-12-010

PRE

Investigation on turbulent heat transfer to lead-bismuth eutectic flows in rough rod bundles for nuclear applications

用于核应用的粗棒束中铅铋共晶流动的湍流传热研究

INTERNATIONAL JOURNAL OF THERMAL SCIENCES

IF5

2024-10-010

PRE

Numerical simulation of the thermal-hydraulic characteristics of the liquid metal flow across the single-start helical coiled tube bundles

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-08-011

PRE

Corrosion products deposition and its effects on conjugate heat transfer for helical cruciform fuel assembly

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-03-014

PRE

Study on two-phase flow instability of parallel helical tubes in steam generator of small modular reactors

INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER

IF6.4

2023-11-0115

PRE

The role of nuclear energy in the carbon neutrality goal

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-08-0170

PRE

Three-dimensional numerical simulation of the interaction between high-pressure sub-cooled water jet impacting high-temperature liquid lead-bismuth metal

APPLIED THERMAL ENGINEERING

IF6.9

2023-07-0112

PRE

An accident diagnosis method of pressurized water reactor based on BI-LSTM neural network

基于bi-lstm神经网络的压水堆事故诊断方法

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-01-012

PRE

Experimental and numerical study of the thermal hydraulics characteristics of a helical-coiled once-through steam generator

APPLIED THERMAL ENGINEERING

IF6.9

2022-11-0118

PRE

Optimization of the thermal-hydraulic performance of zigzag-type microchannel heat exchangers using asymmetric geometry

APPLIED THERMAL ENGINEERING

IF6.9

2022-11-013

PRE

Experimental study on heat transfer and pressure drop characteristics in a microchannel heat exchanger assembly with S-shaped fins

S形翅片微通道换热器组件传热和压降特性的实验研究

APPLIED THERMAL ENGINEERING

IF6.9

2022-06-0115

PRE