Dear FLUKA users
I am reproducing the neutron shielding results obtained with the MCNP code in one article (check the article in Comparison of results for validation should there be a need).
So far I have defined a similar geometry, and I use a similar energy spectrum for the 241Am-Be neutron source.
The problem is with defining the material composition of Polyethylene containing 1.2 % boron carbide (I doubt I got the density of the composition correct).
The ultimate aim is to get the dose rates less than 0.025 mSv/h (=25 uSv/h) outside the geometry if everything is well defined.
Can you please assist in defining this material? Here I provide the flair project and the spectrum data. I used routine provided in Sampling from energy spectra
extr.dat (2.0 KB)
MCNP-results.flair (3.3 KB)