transport approximation
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2019 ◽  
Vol 12 (2) ◽  
pp. 762-787 ◽  
Author(s):  
Léo Lebrat ◽  
Frédéric de Gournay ◽  
Jonas Kahn ◽  
Pierre Weiss

2018 ◽  
Vol 330 ◽  
pp. 806-821 ◽  
Author(s):  
A. Vidal-Ferràndiz ◽  
S. González-Pintor ◽  
D. Ginestar ◽  
C. Demazière ◽  
G. Verdú

2016 ◽  
Vol 685 ◽  
pp. 80-84 ◽  
Author(s):  
Denis O. Dil ◽  
Aleksey M. Bubenchikov

The article describes the numerical approach uniting finite volume method, Newton method and one of the MUSCL-type schemes for convective transport approximation for gas mixture components concentrations displaced by the water out of the porous medium. Numerical and analytical solutions for the case of radial two-dimensional flow of incompressible gas mixture and water have been compared. The obtained results allow considering the offered algorithm to be effective.


2015 ◽  
Vol 299 ◽  
pp. 352-373 ◽  
Author(s):  
Sooyoung Choi ◽  
Kord Smith ◽  
Hyun Chul Lee ◽  
Deokjung Lee

2013 ◽  
Vol 14 (2) ◽  
pp. 59
Author(s):  
Mohamad Ali Shafii

A few numerical methods that usually used to solve neutron transport equation in nuclear reactor are SN dan PN method, Monte Carlo, Collision Probability and Methods of Characteristics . First two methods have been developed using diffusion approach, and last three methods suitable are applicated for transport approximation. Those of three methods have important role in the desain of nuclear reactors. In addition to follow the development of advanced reactor designs, the three methods were chosen because they do not use diffusion approach these are more accurate methods, as well as less need considerable computer memory. Of all the existing methods, the CP method has several advantages among the others. Keywords : Neutron transport, SN, PN, CP, MOC, MC


THERMOPEDIA ◽  
2008 ◽  
Author(s):  
Leonid A. Dombrovsky

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