Results 91 to 100 of about 903 (120)

Retinal degeneration driven by brain-derived neurotrophic factor deficiency in microglia and T-lymphocytes. [PDF]

open access: yesSci Rep
Reinehr S   +9 more
europepmc   +1 more source

Violet Arsenic Phosphorus: Switching p-Type into High Performance n-Type Semiconductor by Arsenic Substitution. [PDF]

open access: yesNanomicro Lett
Zhai R   +9 more
europepmc   +1 more source

Helical Photonic Metamaterials for Encrypted Chiral Holograms. [PDF]

open access: yesAdv Sci (Weinh)
Choi W   +6 more
europepmc   +1 more source

Low-Cost, Compact Quadrupole Mass Filters with Unity Mass Resolution via Ceramic Resin Vat Photopolymerization. [PDF]

open access: yesAdv Sci (Weinh)
Eckhoff CC   +4 more
europepmc   +1 more source
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Development of a flow sweeping mixing model for helical fuel rod bundles

Annals of Nuclear Energy, 2021
Abstract The helical fuel rod is a kind of axially twisted fuel element with a three or four-petaled profile. The helical fuel rod assembly assembled by helical fuel rods against one another in an array is self-supporting and free of spacer grids. This study analyses the flow field in a four-petaled helical fuel rod bundle from a subchannel method ...
Yao Xiao, Junsen Fu
exaly   +2 more sources

Analysis of inter-channel sweeping flow in wire wrapped 19-rod bundle

Nuclear Engineering and Design, 2018
Abstract Helical wire spacers are widely used in sodium cooled fast reactors. One of the main effects of wire spacers is enhancing the inter-channel cross flow in triangular arrayed rod bundles. To study the characteristic of sweeping flow rate across the gaps between the sub-channels, the computational fluid dynamics (CFD) method is used in the ...
Wang, Xi, Cheng, Xu
openaire   +2 more sources

Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers

Annals of Nuclear Energy, 2015
Grid spacers with mixing vanes are used in nuclear fuel assemblies in order to increase the lateral cross-flows between sub-channels that homogenize the temperature distribution within the fuel rod bundle. For the thermal-hydraulic design of such fuel bundles, sub-channel analysis codes are used in order to predict the mass and temperature distribution.
Zimmermann, Markus   +4 more
openaire   +2 more sources

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