Calculating Electron Yield by Photon Saturation in MCNP

  • Thread starter Thread starter Salman Khan
  • Start date Start date
AI Thread Summary
To determine the saturation limit of electron yield from gamma photon incidence on a metal sheet using MCNP, one must analyze the results per particle generated by the simulation. It is feasible to run simulations with varying particle numbers, such as from 10^6 to 10^12, to observe changes in electron yield and identify the saturation point. The saturation limit can be assessed by comparing the yield at different particle counts until a plateau is reached. Proper calibration and understanding of the material properties are essential for accurate results. Ultimately, MCNP can effectively model these interactions to find the saturation limit of electron yield.
Salman Khan
Messages
35
Reaction score
2
TL;DR Summary
Electron yield by photon saturation in mcnp
How to check the the saturation limit of electron yield by gamma photon incident on a metal sheet using mcnp. As I know that mcnp give result per Particle , but how can I check the final saturation limit of that metal. Is it possible to check it for different numbers from 10e6 to 10 e12 to see the saturation limit
 
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...

Similar threads

Back
Top