Using JEFF 2.2 cross sections

User Support
1

Hi All,

I am developing a burnup code that I couple with OpenMC and I am now comparing isotopic density results with benchmarks. There are some discrepancies for certain nuclides and I suspect that it might be caused by the fact that OpenMC uses JEFF3.2 to produce one-group effective cross sections while the benchmarks use older libraries (JEFF2.2, ENDF/B-VI). To be certain that this is the root cause of the discrepancies, I would like to have OpenMC use JEFF2.2 to produce one-group effective cross sections.

Is this possible? Alternatively, I could modify the hdf5 file of the corresponding nuclides and reactions but I am not sure if it is recommended and easy to do this. Any suggestions?

Thanks a lot for your help.

Julien

2

Hi Julien,

I’m trying to generate a library with JEF2.2 data but I’m running into problems with NJOY processing some of these files. I’ll let you know if I get a full library built that you can use.

Best regards,
Paul

3

Hi Paul,

Sorry for the late reply.

Thanks for that. While it’s not urgent, I think it would indeed be useful to be able to use older libraries with OpenMC. The majority of burnup calculation benchmarks have been done with older libraries.

Julien

4

Hi Paul, Do you still have JEFF2.2 data available?? i need it . There isn’t any in the official website.
-Imtiaj

5

@imtiaj_hossain No, unfortunately I don’t think I was ever able to successfully build a JEFF 2.2 library.