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

  • Thread starter Thread starter QEROURI ASSIYA
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QEROURI ASSIYA
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Hii everyone, is there anyone who use the Mesh tally in MCNPX?
 
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Hi and welcome,
Rather than 'ask to ask' it's probably best to describe what you want help with as fully as possible.
 

Thread 'MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly'

Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information（power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.） for Material 2 is zero, while Material 1...
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