MCNP5 vs MCNPX: What's the Difference?

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Discussion Overview

The discussion centers on the differences between MCNP5 and MCNPX, specifically focusing on their applications and functionalities. Participants explore the capabilities of each code, particularly in relation to depletion calculations and the handling of fissile materials.

Discussion Character

  • Exploratory, Technical explanation, Conceptual clarification

Main Points Raised

  • Some participants inquire about the basic differences between MCNP5 and MCNPX.
  • It is noted that MCNPX can be used for depletion calculations.
  • One participant seeks clarification on what depletion calculations entail and requests an example.
  • Another participant explains that depletion refers to the decrease of fissile nuclides over time and involves calculating both the depletion of these nuclides and the accumulation of fission products.
  • The explanation includes the creation of fissile isotopes and other transuranics as part of the depletion process.

Areas of Agreement / Disagreement

Participants express interest in the differences between the two codes and the concept of depletion calculations, but there is no consensus on all aspects of the discussion, particularly regarding the specifics of how each code operates.

Contextual Notes

The discussion does not resolve the complexities of depletion calculations or the full range of differences between MCNP5 and MCNPX, leaving some assumptions and definitions unaddressed.

Who May Find This Useful

Individuals interested in computational methods for nuclear engineering, particularly those working with MCNP codes and depletion calculations.

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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