MCNP5 vs MCNPX: What's the Difference?

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MCNP5 and MCNPX are both Monte Carlo codes used for radiation transport, but MCNPX is specifically designed for depletion calculations, which involve tracking the reduction of fissile materials over time. Depletion calculations account for the fission of nuclei, resulting in the formation of fission products, as well as the creation of new fissile isotopes and transuranics. Understanding these processes is crucial for accurate modeling in nuclear applications. The discussion highlights the importance of these calculations in nuclear physics and engineering. Overall, the thread provides valuable insights into the differences between the two codes and the concept of depletion in nuclear reactions.
Rosenti 87
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Hello everyone,
I need help.
Anyone can explain what is the basic differences between MCNP5 and MCNPX? I appreciate every suggestion for help me. Thanks. Rose
 
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Hi,
You may want to check the link. I hope it works for you.

Best.
 
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the MCNPX can be used for depletion calculations
 
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Thanks a lot "Parazit". The link has helped me.
parazit said:
Hi,
You may want to check the link. I hope it works for you.

Best.
 
Stephan_doc said:
the MCNPX can be used for depletion calculations
Thanks a lot for reply. But, can you explain depletion calculation means? If you don't have any objection, you can explain by example. thx
 
Depletion refers to the decrease, or depletion, of fissile nuclides, e.g., 235U and 239Pu with time. When a nucleus fissions, the result is two new radionuclides, or fission products. So, in addition to depletion, one must calculate the accumulation of fission products. In addition to fission, one also must account to the creation of fissile isotopes, e.g., 239Pu and 241Pu, and other transuranics, e.g., isotopes of Am and Cm.
 
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Thank you Astronuc for the explanation.
 

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