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pro vyhledávání: '"Strizhov, Valery F."'
The SP3 approximation of the neutron transport equation allows improving the accuracy for both static and transient simulations for reactor core analysis compared with the neutron diffusion theory. Besides, the SP3 calculation costs are much less tha
Externí odkaz:
http://arxiv.org/abs/1903.11502
An oxidation process is simulated for a bundle of metal tubes in a cross-flow. A fluid flow is governed by the incompressible Navier-Stokes equations. To describe the transport of oxygen, the corresponding convection-diffusion equation is applied. Th
Externí odkaz:
http://arxiv.org/abs/1708.04138
Modeling of dynamic processes in nuclear reactors is carried out, mainly, on the basis of the multigroup diffusion approximation for the neutron flux. The basic model includes a multidimensional set of coupled parabolic equations and ordinary differe
Externí odkaz:
http://arxiv.org/abs/1706.05226
Publikováno v:
In Nuclear Engineering and Design January 2019 341:326-345
Publikováno v:
In Applied Mathematical Modelling July 2018 59:251-271
Publikováno v:
In Annals of Nuclear Energy January 2017 99:68-79
Autor:
Alipchenkov, Vladimir M., Kiselev, Arkadi E., Strizhov, Valery F., Tsaun, Sergey V., Zaichik, Leonid I.
Publikováno v:
In Nuclear Engineering and Design 2009 239(4):641-647
Akademický článek
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