RE: [fluka-discuss]: Uranium with LOW-MAT for neutrons & HEAVYIONS

From: Vasilis Vlachoudis <Vasilis.Vlachoudis_at_cern.ch>
Date: Mon, 16 Jun 2014 07:18:00 +0000

Dear Vegard,

you have exceeded your weekly quota for questions :)

1. RESNUCLEI: Spalation the manual is self-explanatory. I cannot write anything more
2. Low Energy neutrons are treated separately with the multi-group approach. It will include
   all residual produced by neutron interactions including fission products.
3. "All" correct
4. Number of stopping particles = fall below the threshold
5. From the USRYIELD if you have biasing you cannot get back counts. If you multiply with
   the bin widths you will get the sum of the entries within the bin.
6. Emerging is after an interaction, while region to region is on boundary crossing
7. The output in the _sum.lis and the _tab.lis is self explanatory. Open the files with a text
    editor and you will see the units.
    Please forget the manual for this point, since it refers to the unformatted (binary) files produced
    by FLUKA. All ascii files used for plotting is already normalized and have fluence/energy per primary
   and ONLY if you plot the double-differential then you get fluence/energy/solid angle per primary
8. There is no natural Uranium in the FLUKA database. You have to make a compound with the
    correct 235,238U composition. No need for LOW-MAT cards if you call the materials with the same
    name as in the database
9. Z are included. The particle HEAVYION has always the number 2, but then to decode it you need
    to create a user routine. OR for scoring purposes you can use a filter with the AUXSCORE card

Cheers
Vasilis
________________________________________
From: owner-fluka-discuss_at_mi.infn.it [owner-fluka-discuss_at_mi.infn.it] on behalf of Vegard.Gjerde_at_student.uib.no [Vegard.Gjerde_at_student.uib.no]
Sent: 15 June 2014 18:19
To: fluka-discuss_at_fluka.org
Subject: [fluka-discuss]: Uranium with LOW-MAT for neutrons & HEAVYIONS

Dear Fluka users,

I'm wondering about the material URANIUM from the database. Is it
natural uranium, which contains ~0.7% 235 and ~99.3% 238? I've added
two LOW-MAT cards, one for 235U and one for 238U. Will this be correct?


I'm also wondering about what atomic numbers Z are included in
HEAVYION. Where does it start?


Best regards,
Vegard Gjerde
Received on Mon Jun 16 2014 - 11:27:55 CEST