Huge discrepancy between results with ENDF-B 8.0 and 8.1

Update: I know that absorption is not an issue now, for this is the fuel cell absorption tally:

Therefore I investigate a bit more into this. I tally the nu-fission rate of the fuel cell. This is the result:

Nu-fission is the total production of neutron per fission reaction. Here are the scores for different nuclide in the fuel:

It differs on U232, and that difference is enough to drown the keff.

Quod erad demonstratum :smiley:

Thank you for the help these past days, @wahidluthfi

Best regards,
Chris