Why Does MCNP Delete Surfaces in Hexagonal Fuel Element Simulations?

AI Thread Summary
MCNP is deleting surfaces in hexagonal fuel element simulations due to the presence of coincident surfaces, which is a normal behavior as it eliminates duplicates. This can lead to issues where entire cells are deleted, causing simulation errors like "particle lost" and "geometry error: no cell found." The problem often arises from undefined volumes or overlapping cells in the geometry. To resolve this, it's essential to ensure all cells are properly defined and that there are no gaps or overlaps. Using the MCNP plotting package can help visualize the geometry and identify problematic areas.
AlexFi
Messages
19
Reaction score
5
TL;DR Summary
tried to model gas cooled reactor, MCNP deleting surfaces
Hello
Tried to model gas cooled reactor with hexagonal fuel elements. MCNP keep deleting surfaces (If you could, run my input and check the .txto file) so the simulations won't run
Any advice?
 

Attachments

  • 1-s2.0-S0149197020300962-gr5.jpg
    1-s2.0-S0149197020300962-gr5.jpg
    21.5 KB · Views: 134
  • Lattice_test.txt
    Lattice_test.txt
    1.4 KB · Views: 142
  • delete.png
    delete.png
    40.2 KB · Views: 158
Engineering news on Phys.org
MCNP will delete coincident surfaces, this is normal. It's a bit like you have a table, and a chair, they might be complicated shapes but the bottom of all the legs of the table and the chair will be touching the floor, so you might have a lot of floor level surfaces that are actually all the same. When you build from macro bodies this will happen a lot, MCNP splits these into elementary surfaces and then gets rid of the duplicates.
 
  • Informative
  • Like
Likes berkeman and Grelbr42
Thanks for the explanation. It seems to me that MCNP deleted the entire cell and the simulation won't run because particles got lost. What would be a solution for this?
 
Usually particles getting lost means part of the volume is undefined. In this case there is something beyond cell 9, that isn't defined, and you have no void cell.
 
Made some minor changes, added void cell
Still getting 'particle lost' and 'geometry error:no cell found' error message
 

Attachments

Hi Alex,

Have you got the plotting package for MCNP set up? If you view your file you will see you have dotted lines. It means that MCNP thinks that some cells are not properly defined. They may be such that the cells overlap. Or that there are regions with no cell defined.
 
Hello, I'm currently trying to compare theoretical results with an MCNP simulation. I'm using two discrete sets of data, intensity (probability) and linear attenuation coefficient, both functions of energy, to produce an attenuated energy spectrum after x-rays have passed through a thin layer of lead. I've been running through the calculations and I'm getting a higher average attenuated energy (~74 keV) than initial average energy (~33 keV). My guess is I'm doing something wrong somewhere...

Similar threads

Back
Top