Title of article
Application of the PN method to the matrix form transport equation
Author/Authors
Alexandre D. Caldeira، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2005
Pages
6
From page
1889
To page
1894
Abstract
In this note, the neutron group fluxes are calculated through the implementation of the matrix form transport equation solution by the PN method and the main objective is to obtain accurate numerical results. Some results for two sample problems are graphically presented. A neutron flux to dose conversion is also proposed to simulate irradiation planning.
Journal title
Annals of Nuclear Energy
Serial Year
2005
Journal title
Annals of Nuclear Energy
Record number
406105
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