How to get the scattered dose from concrete using MCNP5?

  • Thread starter Thread starter DF19
  • Start date Start date
  • Tags Tags
    Concrete Mcnp5
AI Thread Summary
To obtain the scattered dose from concrete using MCNP5, the user seeks a method to isolate scattered photons from a point source. They are comparing scattered and direct doses for a point detector in a shielding project. The user has tried using tallies with energy bins but finds it complex to filter only the scattered photons. A proposed solution involves calculating the dose in air alone and then in both air and concrete, subtracting the two to derive the scattered dose from the concrete. The discussion emphasizes the need for effective techniques in MCNP5 for accurate dose assessment.
DF19
Messages
6
Reaction score
0
Hello fellow nuclear engineers and physicists,

Does anyone know how to just get the scattered dose from a surface like concrete using MCNP5? I'm doing a project for a shielding class and I need to compare scattered dose and direct (uncollided) dose for a point detector. The photons are coming from a point source.

I've experimented with tallies associated with energy bins, but it's getting real complicated and I can't find a clever way to filter just the photons scattered from concrete.

My only theory is finding the dose with just air, then finding the dose with the concrete and air and subtracting the two to find the scattered dose from the concrete.
 
Engineering news on Phys.org
Here is my input file, it has the geometry in it.
 

Attachments

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...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
Back
Top