Greetings fellow OpenMC users.
I am designing a (9,9) reactor assembly with a 16 TRISO(u235 enrichment 15.5) fuel assembly. The rest of the assembly contain normal fuel and water in the corner. The problem i am having is in fission reaction rate calculation. I am using each assembly dimension (Z,Y) as one mesh size and calculation for whole Z axis for fission reaction rate defined in my tally.
The reaction rate values i am plotting as (9,9,1) dimension mesh plot in python ans also I am plotting flux as (400,400,1) dimension for the whole core. attached is the flux and reaction rate plots.
The flux plot shows the high flux in the TRISO assemblies but in fission plot, the assemblies showing less reaction rate (showing as blue angular box).
What could be the problem here? Please advise. Thanks.
