Hello, I am trying to generate flux tally with the below code
<?xml version="1.0"?>regular
50 1
<lower_left>-70.71 -70.71</lower_left>
70.71 70.71
1
1
flux
where 70.71 is the radius of my reactor. Now, In the tally.out file I got something
============================> TALLY 1 <============================
Mesh Index (1, 1)
Total Material
Flux 12.2047 +/- 6.30332E-02
Mesh Index (2, 1)
Total Material
Flux 11.7069 +/- 6.12077E-02
…
for the first two mash. And the rest is 0. I want to plot the neutron flux from center to radius of the reactor. I am not getting such values. Am I missing something? If I had the value I would use them to generate a downward plot in Microsoft excel. But, so far I am stuck on not getting the proper data in flux tally. Please help.