MCNP error zero lattice element hit

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Discussion Overview

The discussion revolves around an error encountered in MCNP5 related to a "zero lattice element hit" when attempting to run a hexagonal lattice input file. Participants explore the implications of this error, particularly in the context of lattice configurations and their arrangement within a cylindrical geometry.

Discussion Character

  • Technical explanation
  • Debate/contested

Main Points Raised

  • One participant describes encountering a "zero lattice element hit" error specifically with a hexagonal lattice, while a square lattice runs without issues.
  • Another participant explains that a "zero lattice" indicates that certain areas of the lattice are unfilled, suggesting solutions such as extending the lattice or filling empty wedges with additional materials.
  • A participant expresses gratitude for the assistance and mentions the challenge of limiting the hexagonal lattice to a 7x7 configuration within a circular cluster surface, considering adjustments to the dimensions.
  • Another participant questions the inclusion of fractional pins in the lattice, noting that a typical fuel array would consist of complete pins and expressing curiosity about the rationale behind the current configuration.

Areas of Agreement / Disagreement

Participants present various viewpoints and suggestions regarding the error and lattice configuration, indicating that multiple competing views remain without a clear consensus on the best approach to resolve the issue.

Contextual Notes

Participants discuss the need for adjustments in the lattice dimensions and configurations, but specific assumptions or dependencies on definitions are not fully explored. The discussion does not resolve the mathematical or technical steps needed to address the error.

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TL;DR
I have been encountering "zero lattice element hit" when I try to run it in MCNP5. The input file is provided below. The square lattice runs fine, but the hexagonal does not. Hope someone can help me here. Thank you.
I have been encountering "zero lattice element hit" when I try to run it in MCNP5. The input file is provided below. The square lattice runs fine, but the hexagonal does not. Hope someone can help me here. Thank you.
 

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That was diverting. :biggrin:

You have a hexagonal lattice filling a cylinder.

You have a hexagonal lattice almost filling a cylinder. A "zero lattice" means that nothing has been provided in a part of the lattice that a particle has arrived at. The white wedges have nothing in them. You can either extend the lattice and fill with some more pins. Or you can fill those wedges with something else. Or you can set their importance to zero.

Probably what you want is to define a new universe and fill it with something. Void or zirc or water or whatever makes sense. Then fill past the pins a step in i and j with that new universe.

homeless.png
 
thank you very much for your help...I thought the problem was more complicated than that :). My problem with the hexagonal lattice is that I have to limit it to a 7x7 lattice and try to put it in a "circular" cluster surface. Maybe, it would be easier to adjust the dimensions in the cluster surface (#s 69-72). Again, thank you for your help :)
 
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Out of curiosity, I was wondering about those fractional pins. Do you really want them in there? I would have expected a fuel array to consist of complete pins. With the placement you have, you have 19 complete pins in a nice 3-pins-on-a-side hexagon, and then a bunch of partial pins. What's up with that?
 

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