I need help in solving the problem of the code written with MCNPX 2.6

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The discussion centers on troubleshooting gamma results (719 KeV) using MCNPX 2.6. Users recommend using an F8 tally for accurate energy spectrum simulations, specifically for the germanium cell, while noting that an F4 tally is less suitable. Concerns are raised about the sectioning of the HPGe detector, suggesting it may not be advisable. Additionally, the absence of a proton library for B-11 in the MCNP pack is mentioned, with a suggestion to install a p-B11 library for improved results. Participants encourage further questions for additional assistance.
mo256
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Greetings and Regards

I had trouble getting the gamma results (719 KeV) by mcnpx 2.6 in the article below. Please guide me if possible. Thanks
 

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Hello @mo256 ,
Welcome to physicsforums.

The HPGe has been sectioned and this does not seem like a good idea. I would edit this out. The description from the paper is even stranger but it certainly seems possible to simulate it. Only an energy spectrum is required from the simulation so this is fine.

Normally I would suggest an F4 tally, but the paper specifies F8. This is a better way of doing it. So add an *Fn8:e tally for the germanium cell and add a set of energy bins for this tally.

If you have any other questions please do ask. I or someone else here may be able to answer.
 
Hi,
To calculate a spectrum in Ge, the tally F8 is the right tally.
In the MCNP pack I don't think there is a proton library for B-11, so a model is applied (you can look in your xsdir or your output file). I don't know if this is the problem but you should try installing a p-B11 library to try.
 
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