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

In summary, the manual says that 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.
  • #1
Oliver-BfS
7
0
TL;DR Summary
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
    470 bytes · Views: 153
  • plot pz 0.1.png
    plot pz 0.1.png
    25.6 KB · Views: 174
Engineering news on Phys.org
  • #2
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.
 
  • #3


One possible way to use this feature is to create a non-rectangular lattice for a specific geometry, such as a voxel phantom, by using the zero entry to define the shape of the lattice. This allows for more flexibility in creating complex geometries without having to use irregular shaped cells.

For example, in a voxel phantom with a million lattice elements, you can define the shape of the lattice using the zero entry to create a non-rectangular lattice that perfectly fits the phantom. This eliminates the need for creating an irregular shaped cell and filling it with the lattice, which can be time-consuming and impractical for complex geometries.

Another way to use this feature is to define a lattice with a specific shape and fill the remaining space with other cells. This can be useful for creating void regions within a lattice or for creating a lattice with holes in specific areas.

Overall, the zero entry in the lattice array allows for more flexibility in creating complex geometries and can be useful in various applications.
 

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

1. What is MCNP and how is it used?

MCNP (Monte Carlo N-Particle) is a computer code used for simulating and analyzing the transport of particles through matter. It is commonly used in nuclear engineering, medical physics, and other fields to model radiation interactions and transport.

2. What does it mean to use a value of zero in a fully specified fill?

In MCNP, a "fill" refers to the material that makes up a specific region in the simulation. A fully specified fill means that the material composition and density have been defined. Using a value of zero in this fill means that the region will be empty, or have no material, in the simulation.

3. When would I want to use a value of zero in a fully specified fill?

There are a few situations where using a value of zero in a fully specified fill may be useful. For example, if you want to model an empty space or void in your simulation, or if you want to create a boundary between two materials without having any material present in that region.

4. How do I specify a value of zero in a fully specified fill in MCNP?

In the input file for MCNP, you can use the keyword "void" to specify a value of zero in a fully specified fill. This will tell the code that there is no material present in that region.

5. Are there any limitations to using a value of zero in a fully specified fill?

Yes, there are some limitations to using a value of zero in a fully specified fill. For example, it may not accurately represent the behavior of particles in that region, as there is no material present to interact with them. Additionally, if you are using tallying in your simulation, the region with a value of zero may not contribute to the results.

Similar threads

  • High Energy, Nuclear, Particle Physics
Replies
1
Views
3K
Replies
23
Views
6K
  • Quantum Physics
Replies
1
Views
2K
  • Quantum Interpretations and Foundations
Replies
12
Views
974
Replies
32
Views
7K
  • MATLAB, Maple, Mathematica, LaTeX
Replies
1
Views
3K
Replies
62
Views
6K
  • Quantum Physics
Replies
8
Views
2K
  • Engineering and Comp Sci Homework Help
Replies
6
Views
6K
Back
Top