MCNP: Scoring Energy Fluence on a Radiograph Planar Grid

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To score energy fluence on a rectangular radiograph planar grid in MCNP, the F4 tally combined with the E4 energy binning is recommended. The FIR tally is used for particle flux, but to differentiate between scattered and total radiation, adding an asterisk before the FIRn tally will yield energy flux results in MeV/cm². This method effectively separates the contributions of scattered and total radiation. The discussion highlights the importance of using the correct tally configurations for accurate radiation scoring. Overall, the solution provided allows for precise measurement of energy fluence in MCNP simulations.
Panagiotis
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Hello my friends,

I would like to ask a question about MCNP.

I want to score energy fluence on a rectangular radiograph planar grid. Do you know which tally should I use?

I use FIR tally for particle flux.

Hope you know an answer to my question :)
 
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Hi,
for my part I'll use F4 with E4 tally,
 
PRSB191921 Thank you for your reply.

I want to score scatter and total radiation, that is why I use FIR tally. So now that I want the energy fluence , I want it seperately for scattered and total radiation.
 
solved it.

Just put ' * ' before FIRn tally and the results are energy flux (MeV/cm^2)!
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...

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