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.
 
Hello, I'm currently trying to compare theoretical results with an MCNP simulation. I'm using two discrete sets of data, intensity (probability) and linear attenuation coefficient, both functions of energy, to produce an attenuated energy spectrum after x-rays have passed through a thin layer of lead. I've been running through the calculations and I'm getting a higher average attenuated energy (~74 keV) than initial average energy (~33 keV). My guess is I'm doing something wrong somewhere...
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