Hello, I have a design where my fuel pin is 7.7 and 8.1 and 60 cm in x and y and z-direction. I am trying to get the fission reaction rate for each of the fuel pin with the below code. I have graphite radial reflector and in total of 42 assemblies.
<?xml version=**'1.0' **encoding=**'utf-8'**?>
<mesh id**=“1”>**
regular
7 6 1
<lower_left> -26.95 -24.3 -30.0 </lower_left>
7.7 8.1 60.0
<filter id**=“1” type=“mesh”>**
1
<tally id**=“1” name=“reaction”>**
1
total
After the project build when I run openmc-plot-mesh-tally statepoint.550.h5 I get the attached image, which is wrong cause i checked with the tallies.out file data I see the date are not mached with the color. the second image is what i am supposed to get. see the talliesreaction.out file. Please help.
talliesreaction.out (4.71 KB)