Hi all,
In tallies I get some result as following:
===========================>
Cell 1001
Total Material
Flux 2.46053 +/- 5.21488E-02
===========================>
U-235.12c
Fission Rate 1.05588E-02 +/- 2.64618E-04
All reaction rate tallies (fission, absorption, (n,2n), scatter, etc.) are simply in units of “reactions per source particle”. In a fixed source problem, you likely would know the number of source particles/sec emitted and from that you could determine the number of reactions/sec. For a k-eigenvalue problem, determine the source rate is trickier. See the following discussion for more on that:
https://groups.google.com/d/topic/openmc-users/r5JtjyH9BIM/discussion