Dear Experts,
I wish to learn neutron transport using Fluka.
1. The source is Am-Be source. I started with an alpha particle at (0,0,0) and target is Be-9. How should I score neutron dose rate in air at 1m ? I tried scoring but the results are not matching with literature data. Say, o/p from USRBDX when multiplied with neutron yield and flux to dose rate conversion factor (for average neutron energy 4.4 MeV), i should obtain the neutron dose rate - am I doing it correct ? As I intend to further solve neutron shielding problem, I chose to use a single energy (average for Am-Be source, from literature). (i/p: alpha1ambe.flair)
2. I tried starting with 4.4 MeV neutron in BEAM, I could score neutron dose rate in air. But with HDPE as shield material, I could not get the expected neutron dose rate. (i/p: 2511ambe2b.flair)
Secondly, how to get the gamma dose rate as the decay of C-12* will give 4.43 MeV gamma, how to obtain this gamma and associated gamma dose rate at 1m ?
Please suggest/help. PFA my input files.
Regards,
Raksha Rajput
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Received on Thu Dec 02 2021 - 10:32:46 CET