FLUKA Code : Total Cross Section Calculation

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SUMMARY

The discussion focuses on performing total cross section calculations using the FLUKA Monte Carlo simulation package, specifically for the 24_Mg(n,TOT) reaction. The user has successfully conducted energy deposition calculations with a proton beam on a water target and is now seeking guidance on which FLUKA cards to utilize for cross section calculations. The relevant energy range for neutron particles is specified as 1.02e6 - 5.19e6 eV, and the user is considering several FLUKA cards including USRYIELD, USRBDX, USRBIN, USRCOLL, and USRTRACK for this purpose.

PREREQUISITES
  • Familiarity with FLUKA Monte Carlo simulation package
  • Understanding of nuclear reactions, specifically the 24_Mg(n,TOT) reaction
  • Knowledge of energy deposition calculations in particle physics
  • Basic proficiency in configuring simulation parameters within FLUKA
NEXT STEPS
  • Research the specific functionalities of FLUKA cards: USRYIELD, USRBDX, USRBIN, USRCOLL, and USRTRACK
  • Study the methodology for calculating total cross sections in FLUKA
  • Examine the EXFOR database for comparative analysis of cross section data
  • Explore tutorials or documentation on configuring energy ranges in FLUKA simulations
USEFUL FOR

Researchers and practitioners in nuclear physics, particularly those involved in Monte Carlo simulations, cross section calculations, and energy deposition studies using FLUKA.

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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