Joe,
A receipt (not the answer) seems common to any multi-group MC code - define it
as a compound, i.e.
MATERIAL 1.7 GRAPHITE
COMPOUND -1.0 CARBON GRAPHITE
Two additional questions:
1) Is there now NO way to switch the low-energy neutron transport OFF? (== is it
activated with any valid value of DEFAULTS?)
If yes:
2) Does FLUKA attempt to prepare the low-energy neutron cross-sections EVEN if
the production and transport thresholds are implicitly set above 20 MeV?
Vadim
Joel DeWitt wrote:
> fluka-discuss:
>
> This problem is cited repeatedly on the discussion board:
>
> "Low energy neutron xsec not found for some media"
>
> The solution to this problem, however, is unclear to me. I don't
> understand how a material (graphite) I've added from the Flair
> database does not have low energy neutron cross-sections properly
> associated with it.
>
> Any help in resolving this issue will be helpful since I have other
> inputs with an identical problem.
>
> Joel DeWitt
> Oklahoma State University
> USA
>
>
Received on Tue Apr 14 2009 - 17:59:49 CEST
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