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Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges
GH Yeoh - Experimental and computational multiphase flow, 2019 - Springer
Thermal hydraulic analysis of nuclear reactor core and its associated systems can be
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …
performed using analysis system, subchannel or computational fluid dynamics (CFD) codes …
The performance of airlift pump for the solid particles lifting during the transportation of gas-liquid-solid three-phase flow: A comprehensive research review
IGNB Catrawedarma… - Proceedings of the …, 2021 - journals.sagepub.com
Research about the enhancement of the airlift pump performance by changing the geometry
and operational parameters has drawn considerable attention in recent years. This paper …
and operational parameters has drawn considerable attention in recent years. This paper …
SOPHIA: development of Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications
Lagrangian-based meshless CFD methods have recently been developed and are being
gradually applied to various research areas. In nuclear engineering, the meshless methods …
gradually applied to various research areas. In nuclear engineering, the meshless methods …
Growth and spectra of gravity–capillary waves in countercurrent air/water turbulent flow
Using direct numerical simulation of the Navier–Stokes equations, we analyse the dynamics
of the interface between air and water when the two phases are driven by opposite pressure …
of the interface between air and water when the two phases are driven by opposite pressure …
Experimental study on gas–liquid pressurization characteristics and prediction for critical gas volume fractions of a mixed-flow pump
In the nuclear power system, the gas–liquid two-phase flow appears in the system pipeline
when some unexpected situations such as the loss-of-coolant accident (LOCA) occur. Under …
when some unexpected situations such as the loss-of-coolant accident (LOCA) occur. Under …
Statistical characterization of liquid film fluctuations during gas-liquid two-phase counter-current flow in a 1/30 scaled-down test facility of a pressurized water reactor …
AH Astyanto, JAE Pramono, I Catrawedarma - Annals of Nuclear Energy, 2022 - Elsevier
The present work investigates the statistical characteristics of the fluctuations of the liquid
film thickness obtained by resistive-conductance probe signals of a complex geometry …
film thickness obtained by resistive-conductance probe signals of a complex geometry …
An experimental study on the effect of liquid properties on the counter-current flow limitation (CCFL) during gas/liquid counter-current two-phase flow in a 1/30 scaled …
AH Astyanto, KV Kirkland - Nuclear Engineering and Design, 2022 - Elsevier
To promote the safety of the nuclear reactors, numerous authors have carried out
investigations of gas/liquid counter-current two-phase flow in order to understand the …
investigations of gas/liquid counter-current two-phase flow in order to understand the …
Modelling and analysis of an endothermic reacting counter-current flow
EK Luckins, JM Oliver, CP Please… - Journal of fluid …, 2022 - cambridge.org
We study the endothermic reaction and flow of a granular solid reactant, where energy for
the reaction is provided by a counter-current flow of hot gases through the porous reactant …
the reaction is provided by a counter-current flow of hot gases through the porous reactant …
Interfacial behavior of the air-water counter-current two-phase flow in a 1/30 scale-down of pressurized water reactor (PWR) hot leg
The study on the interfacial phenomena of flooding during the counter-current flow of gas-
liquid in a complex pipe was carried-out experimentally. It consists of a combination of the …
liquid in a complex pipe was carried-out experimentally. It consists of a combination of the …
[HTML][HTML] Reprint of “The role of nuclear thermal-hydraulics in the licensing of Atucha-II: The LBLOCA”
O Mazzantini, G Galassi, F D'Auria - Nuclear Engineering and Design, 2019 - Elsevier
The paper deals with the safety evaluation and the embedded licensing process of the
Atucha-II 800 Mwe Pressurized Heavy Water Reactor (PHWR) in Argentina. Atucha-II was …
Atucha-II 800 Mwe Pressurized Heavy Water Reactor (PHWR) in Argentina. Atucha-II was …