MCNP4 Trouble -- Zero results with tally type 4

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Calculating flux in a bioshield cell is yielding zero results for the user, specifically for parameters f44 and f54. The community emphasizes the necessity of providing the complete input file to diagnose the issue effectively. Without the full context, troubleshooting becomes challenging. The discussion highlights the importance of sharing all relevant data for accurate assistance. Providing the complete input file is essential for resolving the calculation problem.
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mcnp zero results with tally type 4
hello. I am trying to calculaty flux in bioshield cell but i get zero (f44, f54) and i can't figure out the reason please help :) txt file is a part of the code
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If you don't provide the full input file, we can't run it to work out what might be the problem.
 
agree with Alex A
 
What type of energy is actually stored inside an atom? When an atom is split—such as in a nuclear explosion—it releases enormous energy, much of it in the form of gamma-ray electromagnetic radiation. Given this, is it correct to say that the energy stored in the atom is fundamentally electromagnetic (EM) energy? If not, how should we properly understand the nature of the energy that binds the nucleus and is released during fission?

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