Re: [fluka-discuss]: use usrtrack card to obtain reaction counts

From: Francesco Cerutti <Francesco.Cerutti_at_cern.ch>
Date: Thu, 8 Aug 2019 09:36:17 +0200

Hallo,

not USRTRACK (which is meant for spectrum scoring), rather USRBIN (per
region - to get the fission counts in each region - or
Cartesian/cylindrical - to get a spatial distribution of fission density),
as indicated in the manual. With the dedicated generalised particles
FISSIONS, HE-FISS and LE-FISS.

Best regards

Francesco Cerutti
**************************************************
CERN-EN/STI
CH-1211 Geneva 23
Switzerland
tel. +41 22 7678962

On Wed, 7 Aug 2019, 李立华 wrote:

>
> Dear fluka experts:
>
>     Can the reaction counts such as fission counts be obtained throught using
> usrtract card,
>
> in mcnp the reaction counts can be obtained throught F4 card,for example,the
> fission counts
>
> can be obtained like this:
>
> F4:n    cell number
>
> fm4 -v material number -6(total fission cross-section)
>
> thanks!
>
>
>
>
>
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Received on Thu Aug 08 2019 - 10:43:41 CEST

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