My goal is to determine the 2-group integrated microscopic cross sections for some isotopes in my system.

My system is simplified; it's just a cubic cell filled with a mixture of my isotopes. The relevant parts of code for geometry and material are as follows (don't focus on the compositions, it is simplified on purpose:

Code: Select all

```
% --- Cross section data library file path:
set acelib "[path].xsdata"
surf 300 cube 0.0 0.0 0.0 5
cell 300 0 my_material -300
cell 900 0 outside 300
my_material -5
3006.12c 0.005
3007.12c 1
4009.12c 0.5
9019.12c 2
92235.09c 0.1
92238.09c 0.5
% --- Neutron population and criticality cycles:
% Reflecting boundary conditions
set bc 2
set pop 10000 300 50
```

Code: Select all

```
mat Li6_XS 1.0
3006.12c 1.0
% Energy Grids
ene fast 1 0.625E-6 200
ene thermal 1 0.0 0.625E-6
% Flux
det f_flux_Li6 dm Li6_XS du 0 de fast
det f_phiXS_Li6 dr 105 dm Li6_XS du 0 de fast
dt 3 f_flux_Li6
```

Can I ask your help?

Best,

Lorenzo