Re: [fluka-discuss]: Source.f user routine for neutrons

From: Beatrice Pomaro <beatrice.pomaro_at_dicea.unipd.it>
Date: Fri, 02 Aug 2024 18:57:04 +0200

Dear Konstantin,
thank you very much for your help. I have added card LOW-MAT (attched
file) but I get the following error message: "undefined atomic density
for the low en. xsec mat. corresponding to the comp. mat. n. 27". Do you
have a suggestion also for that?
Thank you very much,
Kind regards,
Beatrice

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**************************************************
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
Il 02-08-2024 11:06 Konstantin Batkov ha scritto:
> Also, if you are interested in accurate neutron transport below a few 
> eV, you need to define a thermal scattering kernel for your wall 
> material. Otherwise, FLUKA assumes the free gas approximation. To do 
> this, specify the wall temperature (room temperature?) and the 
> crystal/molecular bound states (hydrogen in a water molecule in your 
> case). If you use groupwise neutron transport, do this with the LOW-MAT 
> card with the 1 1 296 identifiers (see table 10.3). In the case of 
> pointwise transport, define the appropriate TSL-PWXS card (the LOW-MAT 
> card is not needed in this case) and, of course, use pointwise energy 
> binning in your estimators:
> TSL-PWXS 1.0  1.0  296.0  PORTLAND
> 
> Konstantin

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Received on Fri Aug 02 2024 - 20:46:51 CEST