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Experimental Evaluation of Thermal Conductivity and Other Thermophysical Properties of Nanofluids Based on Functionalized (-OH) Mwcnt Nanoparticles Dispersed in Distilled Water
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作者 Alexandre Melo Oliveira Amir Zacarias Mesquita +2 位作者 João Gabriel de Oliveira Marques Enio Pedone Bandarra Filho daniel artur pinheiro palma 《Advances in Nanoparticles》 CAS 2023年第1期32-52,共21页
A possible way to increase thermal conductivity of working fluids, while keeping pressure drop at acceptable levels, is through nanofluids. Nanofluids are nano-sized particles dispersed in conventional working fluids.... A possible way to increase thermal conductivity of working fluids, while keeping pressure drop at acceptable levels, is through nanofluids. Nanofluids are nano-sized particles dispersed in conventional working fluids. A great number of materials have potential to be used in nanoparticles production and then in nanofluids;one of them is Multi-Walled Carbon Nano Tubes (MWCNT). They have thermal conductivity around 3000 W/mK while other materials used as nanoparticles like CuO have thermal conductivity of 76.5 W/mK. Due to this fact, MWCNT nanoparticles have potential to be used in nanofluids production, aiming to increase heat transfer rate in energy systems. In this context, the main goal of this paper is to evaluate from the synthesis to the experimental measurement of thermal conductivity of nanofluid samples based on functionalized (-OH) MWCNT nanoparticles. They will be analyzed nanoparticles with different functionalization degrees (4% wt, 6% wt, and 9% wt). In addition, it will be quantified other thermophysical properties (dynamic viscosity, specific heat and specific mass) of the synthetized nanofluids. So, the present work can contribute with experimental data that will help researches in the study and development of MWCNT nanofluids. According to the results, the maximum increment obtained in thermal conductivity was 10.65% in relation to the base fluid (water). 展开更多
关键词 Nanofluids Multi-Walled Carbon Nano Tubes (MWCNT) Functionalization Degree Thermal Conductivity Thermophysical Properties
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A New Formulation to the Point Kinetics Equations Considering the Time Variation of the Neutron Currents
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作者 Anderson Lupo Nunes Aquilino Senra Martinez +1 位作者 Fernando Carvalho da Silva daniel artur pinheiro palma 《World Journal of Nuclear Science and Technology》 2015年第1期57-71,共15页
The system of point kinetics equations describes the time behaviour of a nuclear reactor, assuming that, during the transient, the spatial form of the flux of neutrons varies very little. This system has been largely ... The system of point kinetics equations describes the time behaviour of a nuclear reactor, assuming that, during the transient, the spatial form of the flux of neutrons varies very little. This system has been largely used in the analysis of transients, where the numerical solutions of the equations are limited by the stiffness problem that results from the different time scales of the instantaneous and delayed neutrons. Its derivation can be done directly from the neutron transport equation, from the neutron diffusion equation or through a heuristics procedure. All of them lead to the same functional form of the system of differential equations for point kinetics, but with different coefficients. However, the solution of the neutron transport equation is of little practical use as it requires the change of the existent core design systems, as used to calculate the design of the cores of nuclear reactors for different operating cycles. Several approximations can be made for the said derivation. One of them consists of disregarding the time derivative for neutron density in comparison with the remaining terms of the equation resulting from the P1 approximation of the transport equation. In this paper, we consider that the time derivative for neutron current density is not negligible in the P1 equation. Thus being, we obtained a new system of equations of point kinetics that we named as modified. The innovation of the method presented in the manuscript consists in adopting arising from the P1 equations, without neglecting the derivative of the current neutrons, to derive the modified point kinetics equations instead of adopting the Fick’s law which results in the classic point kinetics equations. The results of the comparison between the point kinetics equations, modified and classical, indicate that the time derivative for the neutron current density should not be disregarded in several of transient analysis situations. 展开更多
关键词 REACTOR Point-Kinetics NEUTRON Current DENSITY NUCLEAR Power DENSITY
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Evaluation of Nuclear Fuel Centerline Temperature Using New UO2 Thermal Conductivity Models
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作者 daniel artur pinheiro palma Amir Zacarias Mesquita +1 位作者 Franciole da Cunha Marinho Marcelo da Silva Rocha 《Journal of Energy and Power Engineering》 2014年第6期1054-1058,共5页
关键词 二氧化铀 核燃料 热导率 模型 安全经济运行 热机械性能 评价 中央
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