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QEROURI ASSIYA
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Hii everyone, is there anyone who use the Mesh tally in MCNPX?
The Mesh tally in MCNPX is a feature that allows users to divide their model into smaller, more manageable sections for radiation transport calculations. It is particularly useful for complex geometries and can provide more accurate results compared to other tally options.
The Mesh tally works by dividing the model into a grid of smaller cells. The user can specify the size and shape of these cells, as well as the material properties within each cell. The tally then calculates the radiation transport through each cell and provides results for each individual cell, as well as the overall model.
One of the main advantages of using the Mesh tally is its ability to handle complex geometries. It also provides more detailed results compared to other tally options, as it calculates the radiation transport through each individual cell. Additionally, the Mesh tally allows for more precise control over the material properties within each cell, which can lead to more accurate results.
Yes, there are some limitations to using the Mesh tally. It can be more computationally intensive compared to other tally options, so it may take longer to run simulations. Additionally, it may not be suitable for all types of models and may require some expertise to properly set up and interpret the results.
There are several resources available for learning more about using the Mesh tally in MCNPX. The MCNPX user manual provides detailed instructions and examples for using the Mesh tally. Additionally, there are online tutorials and forums where users can share tips and ask questions about using the Mesh tally. It may also be helpful to attend workshops or training courses on MCNPX to learn more about this feature.