Changes between Version 8 and Version 9 of GuarDyan_features

Timestamp:

Aug 24, 2017, 2:00:13 PM (7 years ago)

Author:

dieda

Comment:

--

GuarDyan_features

@@ -39 +39 @@
 
 ''' 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.
+
+In current implementation GUARDYAN stores the energy partitioning structure separately for every isotope. To find
+the cross section of a neutron with given energy GUARDYAN useS 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.
+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
 
+Considering the most important isotopes in a e.g.  VVER-440 reactor with fresh fuel: 1H, 2H, 4He,10B, 11B 16O, 17O, 90Zr, 91Zr, 92Zr, 94Zr, 96Zr, 93Nb, 152Gd, 154Gd, 155Gd, 156Gd, 157Gd, 158Gd, 160Gd,174 Hf, 176Hf, 177Hf, 178Hf, 179Hf, 180Hf,235 U, 238U, with 8 different materials definedto store the cross section data for a given temperature 102,4 MB memory is needed on the GPU. For a realistic VVER-440 power plant with full detailed modelling the cross section date reaches 5Gb in memory need. The videocards available contain 2 (GTX 690) or 8 (GTX 1080) GB memory each for realistic simulations therefore modern videocards offer enough physical memory.
 
 == Variance Reduction