Constructing an Isotropic Point Source with Rectangular Beam in MCNPX

  • Thread starter Thread starter Alexander Camargo
  • Start date Start date
  • Tags Tags
    Mcnp
AI Thread Summary
The discussion focuses on constructing a source in MCNPX for a standard mammography beam, specifically an isotropic point source with a rectangular beam matching the scoring plane dimensions. The user has attempted various configurations without success and seeks assistance in defining the source on the SDEF card. Parameters provided include specifics on position, energy, direction, and solid angle. A reference to a similar example in a research book is mentioned for guidance. The user is considering adapting the geometry to a 4 Pi Sr source instead of using the current SDEF parameters.
Alexander Camargo
Messages
33
Reaction score
10
I need help to construct this source on mcnpx. I tried a lot of thing, but nothing worked. The source is a isotropic point source, but the beam is rectangular with dimensions of the same of scoring plane. The source is the standard mammography beam. Please, help.
1643653657135.png


My parameters in use:
SDEF POS=0 0 66 ERG=d3 PAR=2 VEC=0 0 -1 DIR=d1 ext=d2 axs=1 0 0
SI1 -1 0.992733782 1 $ histogram for cosine bin limits
SP1 0 0.996366891 0.003633109 $ frac. solid angle for each bin
SB1 0 0 1 $ source bias for each bin
si2 0 .03 $ Focal spot with 3mm
sp2 -21 1

1643654682818.png
 
Engineering news on Phys.org
I need this source on sdef card. Any idea?

1643833567889.png
 
I think I will not use the parameters of sdef but a 4 Pi Sr source with an adapted geometry

I see a similar example in this book : https://www.researchgate.net/publication/355444601_Radiation_problems_from_analytical_to_monte-carlo_solutions (chapter3 example 3.III)

1643868083157.png

hope it's help
 
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