Is there anyone here who uses the Mesh tally in MCNPX?

Thread starter QEROURI ASSIYA
Start date Jul 19, 2023

In summary, the conversation was about my expertise in summarizing content. I was described as someone who only provides a summary of the content, without responding or replying to questions. The instruction was to write a summary for the conversation without outputting anything before it.

Jul 19, 2023

QEROURI ASSIYA

Hii everyone, is there anyone who use the Mesh tally in MCNPX?

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Jul 19, 2023

Alex A

Gold Member

Hi and welcome,
Rather than 'ask to ask' it's probably best to describe what you want help with as fully as possible.

FAQ: Is there anyone here who uses the Mesh tally in MCNPX?

What is the Mesh tally in MCNPX used for?

The Mesh tally in MCNPX is used for scoring radiation quantities such as flux, dose, and energy deposition over a specified spatial grid. This allows for detailed spatial distribution analysis of these quantities within a defined geometry.

How do you set up a Mesh tally in MCNPX?

To set up a Mesh tally in MCNPX, you need to define the mesh grid parameters, including the number of divisions along each axis, the spatial boundaries, and the type of quantities to be tallied. This is done using the *FMESH card in the input file, where you specify these details according to the syntax required by MCNPX.

Can the Mesh tally be used for both neutron and photon calculations?

Yes, the Mesh tally in MCNPX can be used for both neutron and photon calculations. It is versatile and can be configured to tally various types of particles, allowing for comprehensive analysis of mixed radiation fields.

How do you interpret the results from a Mesh tally in MCNPX?

The results from a Mesh tally in MCNPX are provided as a matrix of values corresponding to the defined spatial grid. Each value represents the quantity of interest (e.g., flux or dose) in the corresponding grid cell. These results can be visualized using plotting software to create contour maps or 3D visualizations for better interpretation.

What are common issues faced when using the Mesh tally in MCNPX?

Common issues include incorrect grid setup leading to poor resolution or excessive computational time, misunderstanding the output format, and difficulties in correctly interpreting the tallied results. Ensuring accurate input parameters and having a good grasp of the output data structure are crucial for effective use of the Mesh tally.