Dear Fluka experts,
I would like to simulate the diffusion of neutrons across a concrete
wall (please, see attached .inp file).
I would like to use a neutron spectrum that consists of 2 kinetic
levels, only: a fast neutron flux of 3.2 × 10^10 n∕(cm2 s) and a thermal
neutron flux of 4.0×10^10 n∕(cm2 s).
How can I modify the source.f subroutine coherently?
And is it correct to use the BEAM card as NEUTRON with a generic energy
level of 100MeV, as the maximum energy expected in the current run,
before recalling the SOURCE card?
Many thanks for your help,
Kind regards,
Beatrice
--
**************************************************
Ing. Beatrice Pomaro
Universita' degli Studi di Padova
Dipartimento di Ingegneria Civile, Edile e Ambientale
Via F. Marzolo, 9 - 35131 Padova (Italy)
tel.: +39 049 8275601
e-mail: beatrice.pomaro_at_dicea.unipd.it
__________________________________________________________________________
You can manage unsubscription from this mailing list at
https://www.fluka.org/fluka.php?id=acc_info
Received on Thu Aug 01 2024 - 17:28:01 CEST