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Small-World Features of Real-World Networks
Wenjun Xiao,Meisheng Li,Guanrong Chen 한국통신학회 2017 Journal of communications and networks Vol.19 No.3
It is well known that there are a large number of complex networks that have vertex-degree distributionsin a power-law form of $ck^{-\gamma}$, where $\emph{k}$ is the degree variable and $\emph{c}$ and $\gamma$are scaling and exponent constants. Recently, we found that it is effective to reveal the underlyingmechanism of power-law formation in real-world networks by analyzing their vertex-degree sequences. We showed before that, for a scale-free network of size \emph{N}, if its vertex-degree sequence is$ k_{1}<k_{2}<{\cdots}<k_{l} $, where $\{k_{1},k_{2},{{\cdots}},k_{l}\}$ is the set of all non-equal vertex degreesin the network, and if its power exponent satisfies $\gamma>1$, then the length \emph{l} of the abovevertex-degree sequence is of order $\log N$. We underline that this conclusion is important, which proves thatthe length of the vertex-degree sequence is a fundamental characteristic of a scale-free network. In this paper,we further investigate complex networks with more general distributions and we prove that the same conclusionabout the vertex-degree sequences holds even for non-network type of complex systems. We thereby conclude thatreal-world networks typically possess small-world features. We support this conclusion by verifying a largenumber of real-world networks and systems. To that end, we discuss some potential applications of the new findingin various fields of science, engineering and society, demonstrating that the conclusion is important with manyreal applications.
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Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Chen Chao,Mei Huaping,He Meisheng,Li Taosheng 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.12
Heat pipe cooled nuclear reactor has been a very attractive technical solution to provide the power for deep space applications. In this paper, a 200 kWe space nuclear reactor power design has been proposed based on the combination of an integrated UN ceramic fuel, a heat pipe cooling system and the Stirling power generators. Neutronics and thermal analysis have been performed on the space nuclear reactor. It was found that the entire reactor core has at least 3.9 $ subcritical even under the worst-case submersion accident superimposed a single safety drum failure, and results from fuel temperature coefficient, neutron spectrum and power distribution analysis also showed that this reactor design satisfies the neutronics requirements. Thermal analysis showed that the power in the core can be successfully removed both in normal operation or under one or more heat pipes failure scenarios.
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