MCNP Barrel Geometry Help

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SUMMARY

The discussion focuses on troubleshooting geometry issues in an MCNP (Monte Carlo N-Particle Transport Code) input deck. Key points include the necessity of a void cell with importance 0 and ensuring that every point in space belongs to a single cell. Users highlighted the importance of correctly defining materials and avoiding extra blank lines before material cards, as well as adhering to the 80-character limit for line lengths. The conversation emphasizes the need for precise geometry and material definitions to prevent fatal errors in the MCNP simulation.

PREREQUISITES
  • Understanding of MCNP input deck structure
  • Familiarity with geometry definitions in MCNP
  • Knowledge of material card specifications in MCNP
  • Awareness of the 80-character line limit in MCNP coding
NEXT STEPS
  • Review MCNP geometry definitions and void cell requirements
  • Learn about proper material card formatting in MCNP
  • Investigate common errors in MCNP input decks and their resolutions
  • Explore best practices for organizing MCNP code to avoid syntax errors
USEFUL FOR

MCNP users, nuclear engineers, and researchers involved in radiation transport simulations who need to troubleshoot and optimize their input decks.

wtobias
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Hey all. I am creating an MCNP input deck but my geometry is appearing red in the vised plot and I am receiving errors relating to the geometry and material card sections. Could anyone potentially help me figure this issue out?
 

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Hi @wtobias, welcome to PhysicsForums!

All problems need a void cell with importance 0, or particles transport forever. Every point in space must belong to only one cell and all space must be in a cell.

You are using surface 1 and 3 in what feels like inconsistent ways. I've ignored surface 1, and putting it back in is your job. If you need a cell between these think about what you need to do to create that.

For cell 111 to not include any of the rods, you have to mention them all. For example,
Code:
  111     0         -3 2
       #51 #52 #53 #54 #55 #56 #57 #58 #59 #60
       #61 #62 #63 #64 #65 #66 #67 #68 #69 #70
       #71 #72 #73 #74 #75 #76 #77 #78 #79 #80
       #81 #82 #83 #84 #85 #86 #87 #88 #89 #90
       #91 #92 #93 #94 #95 #96 #97 #98 #99 #100
       #91 #92 #93 #94 #95 #96 #97 #98 #99 #100
       #101 #102 #103 #104 #105 #106 #107 #108 #109 #110 imp:n=1

I've used cell 50 as the central rod and added 999 as the void. Does this start to make sense?
 

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Last edited:
Yes thank you that makes sense. I still run into a fatal error when defining the materials however. I define material 1 for cell 111 and material 2 for the new cell I made 112. I'm not exactly sure where I am going wrong with my input. Ill provide the updated copy of the code below that sends the error. all that was changed was the material definition in the cell section for cells 111 and 112.
 

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You have an extra blank line just before the material cards and the program stops reading. One blank after the cell definitions and one after the surface definitions is all you should have. There is also stuff beyond the 80 char limit, which makes my version unhappy, but a new copy might be fine with that. It was an old IBM mainframe punched card limitation. Lastly there are too few spaces here
Code:
   24052.80c -0.18 $ 18% Chromium for SS 304
   28058.80c -0.12 $ 12% Nickel for SS 304
5 spaces will tell the code you are continuing the last line.
 
This helped thank you
 
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