FLUKA Code : Total Cross Section Calculation

AI Thread Summary
The discussion centers on using the Fluka Monte Carlo simulation package to calculate the total cross section for the 24_Mg(n,TOT) reaction, with a focus on comparing results to EXFOR data. The user has successfully conducted energy deposition calculations with a proton beam on a water target and is now looking to run simulations for neutron particles in the energy range of 1.02e6 - 5.19e6 eV. The main challenge lies in selecting the appropriate Fluka cards for cross section calculations, with options including USRYIELD, USRBDX, USRBIN, USRCOLL, and USRTRACK. The user seeks guidance on which card to use and expresses a willingness to receive any assistance or insights from the community.
parazit
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Hi folks,

I'm working on Fluka nowadays which you can found from here if you are not familiar. It's a very useful and widely used Monte Carlo simulation package.

My main goal is to be able to perform total cross section calculation with it. So far, please consider I'm a rookie, I've done some calculations about energy deposition such as a proton beam hitting to a water target. I really would like to perform a calculation about the total cross section for the 24_Mg(n,TOT) reaction and compare the results with the EXFOR data. The energy range of n particles from EXFOR is between 1.02e6 - 5.19e6 eV which means I have to run the Fluka between those energy ranges. It seems ok, I am able to arrange the energy of incoming particles but the main issue is which card am I going to use to get the cross section calculation from Fluka.

Here are some possible cards that I'm still working on them :
- USRYIELD
- USRBDX
- USRBIN
- USRCOLL
- USRTRACK

So anyone who has something to say about that, any kind of help is sincerely accepted.

Best wishes.
 
I think that has already been worked out and readily available. What do you need the data for, or are you just trying to verify Fluka?
 
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