Changes between Version 7 and Version 8 of GuarDyan_features

Timestamp:

Aug 22, 2017, 4:57:04 PM (8 years ago)

Author:

dieda

Comment:

--

GuarDyan_features

@@ -36 +36 @@
 Cells are considered homogeneous and filled with a single material defined by the isotopes, their relative abundance and material density. Cross sections are read from ACE format files. 
 
+[[Image(XS.png, 50%)]]
+
+''' Fig. 2. Cross section of U-235 as read by GUARDYAN'''
+In current implementation we store the energy partition separately for every isotope. To find
+the cross section of a neutron with given energy we use binary search and linear interpolation.
+
+GUARDYAN createS materials from isotopes using the fraction of the constituent in the material
+and the material density. Before the simulation GUARDYAN generates the total macroscopic cross sections and the majorant cross sections (for the Woodcock method) for every material.
+
+==== Memory Use of Cross Section Data
+
 
 == Variance Reduction