MCNP: How to use value zero in a fully specified fill

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SUMMARY

The discussion centers on the use of a zero value in the lattice array of MCNP6.2, which indicates that a lattice element does not exist, allowing for non-rectangular arrays. The user seeks to define a finite lattice that consists of three specific cells while utilizing the remaining space for other cells, a challenge compounded by the limitations of MCNP6.1, which lacks the features of version 6.2. The user notes that the lattice appears infinitely large in the MCNP plotter, raising questions about its intended size. The inability to use a zero entry effectively in a fully specified fill is highlighted as a significant limitation.

PREREQUISITES
  • Understanding of MCNP6.1 and MCNP6.2 functionalities
  • Familiarity with lattice definitions in MCNP
  • Knowledge of cell definitions and fills in MCNP
  • Experience with plotting in MCNP
NEXT STEPS
  • Research the differences between MCNP6.1 and MCNP6.2 features
  • Explore the MCNP6.2 manual, specifically page 3-37 regarding lattice definitions
  • Investigate how to effectively use zero values in lattice arrays
  • Learn about defining irregular shaped cells in MCNP for complex lattices
USEFUL FOR

This discussion is beneficial for MCNP users, particularly those involved in nuclear engineering, radiation transport simulations, and anyone looking to optimize lattice configurations in MCNP models.

Oliver-BfS
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TL;DR
When an entry of zero is used in a fully specified fill, how can the position of the missing cell be defined with another cell?
The MCNP6.2 manual (page 3-37) says: "There are two nj values that can be used in the lattice array that have special meanings. A zero in the level-zero (real world) lattice means that the lattice element does not exist, making it possible, in effect, to specify a non-rectangular array."

How can this feature be used? Usually I put the lattice, which is infinitely large, into a universe and fill another cell with finite extent with this lattice. This makes the lattice finite. However, for using a zero entry in the fully specified fill this is not possible because the lattice must be in the real world, not in a universe.

When I define a lattice as in the attached input file, it is infinitely large and three cells ((1,0,0),(0,1,0), (1,1,0)) are defined whereas all other cells are undefined, even if I add another cell for all other space except of the lattice (using the # operator together with the lattice cell number).

(I wonder if the lattice is really meant to be infinitely large or if it is meant to be confined to the three defined cells. However, it is plotted with infinite extent in the MCNP plotter.)

So how can I define a lattice that consists of the three cells and which allows the remaining space to be used for other cells?

(Defining an irregular shaped cell and filling this cell with the lattice in order to clip everything outside this cell is not an option. First of all, this would make the zero entry useless. Second, this is possible for the simple example with four cells but certainly not for more complicated lattices such as a voxel phantom with a million of lattice elements.)
 

Attachments

  • input.txt
    input.txt
    470 bytes · Views: 225
  • plot pz 0.1.png
    plot pz 0.1.png
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I have just observed that I did not use MCNP6.2 but 6.1 for that problem. (6.2 is not available for me at the moment.) So maybe that feature was newly introduced with version 6.2. However, I cannot find information about that in the 6.2 release notes and the manual of version 6.1 is not available online.
 

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