I have a problem on my MCNP5 cross-section library

In summary, the speaker is having trouble running input files with materials containing elements with atomic numbers 34000 and 52000 in their MCNP5 cross-section library. They suggest building the materials using individual isotopes or finding a substitute material. It is also possible to search for the data online and use the isotope library utilities in MCNP to add it to the library.
  • #1
Islam Nabil
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TL;DR Summary
i have a problem on my MCNP5 cross-section library
I have a problem with my MCNP5 cross-section library. Se and Te elements with atomic numbers; 34000 and 52000, respectively, have no neutron cross-section stored, either neutron contentious or neutron other, in the library, and so I can't run any input file that has any material of them because of the neutron cross-section.!!
 
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34000 and 52000 indicate the natural form of these elements. That is, it is asking MCNP to look for the natural isotope distribution library for Se and Te. Several of the natural substances are not there while the individual isotopes are there.

Depending what is in your library, you have some choices. If the individual isotopes are there, you could build your material out of them. So, Se for example: https://en.wikipedia.org/wiki/Selenium

You could look in your lib for 34074. 34076, 34077, 34078, 34080, and 34082. If they are all there you can build natural Se out of them. Pretty close, anyway.

If those isotopes are not in your library, you can try to find a material that you can substitute. That's a fairly complicated thing. And it's difficult to be confident if you don't have any data to guide you. Maybe if only some of those isotopes are present, you could build a partial model, maybe using the more common isotopes.

If you are keen, and need these isotopes, and you have the time, you could see if the data exists somewhere on line. Then you could learn the isotope library utils that come with MCNP. NJOY is one of them.
 
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FAQ: I have a problem on my MCNP5 cross-section library

Why is my MCNP5 simulation not running after updating the cross-section library?

This issue often arises due to mismatched or corrupted data files. Ensure that the cross-section library files are correctly formatted and compatible with MCNP5. Verify that the path to the cross-section library is correctly specified in the input file.

How do I convert ENDF/B-VII cross-sections to be used in MCNP5?

To convert ENDF/B-VII cross-sections for use in MCNP5, you can use the NJOY processing code. NJOY can process these cross-sections into ACE format, which is required by MCNP5. Detailed instructions for using NJOY can be found in the NJOY user manual.

What should I do if my MCNP5 cross-section library is missing certain isotopes?

If your cross-section library is missing isotopes, you can either find a library that includes these isotopes or generate the necessary data using NJOY. Make sure to follow the guidelines for creating ACE files compatible with MCNP5.

How can I verify that my cross-section library is correctly implemented in MCNP5?

To verify that your cross-section library is correctly implemented, you can run a simple test case with known results. Compare the output to expected values or results from a verified source. Additionally, check the MCNP5 output file for any warnings or errors related to the cross-section data.

What are the common errors related to cross-section libraries in MCNP5 and how can I fix them?

Common errors include "file not found," "invalid format," and "incompatible data." To fix these, ensure that the library files are correctly named and located in the specified directory, that they are in the correct ACE format, and that they are compatible with the version of MCNP5 you are using. Double-check the input file for correct paths and filenames.

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