Decay Rate missed some values in tallies for Decay Rate

Validation and Verification
1

hello everybody,
I’m using OpenMC 13.0 version.
I’m trying to get the decay rate for six delayed groups.
I don’t understand why OpenMC could not give all values for decay rate , and give this value as -nan +/- 0 in (tallies.out) file. specially when do
materials.zip_.xml (1.8 MB)
run by mpirun.

Has anyone have an explanation ?
change_1.py (753 Bytes)
geometry.xml (101.4 KB)
settings.xml (285 Bytes)
tallies.xml (528 Bytes)

Help me, please.
Thank you.

tallies
tallies1200×1200 268 KB

2

@shatnawihamza I ran your problem with OpenMC 0.13.2 and I seem to be getting reasonable results for the decay rates:

 ============================>     TALLY 1     <============================

 Universe 317
   Delayed Group 1
     Total Material
       Delayed-Nu-Fission Rate              0.00025782 +/- 7.49041e-07
   Delayed Group 2
     Total Material
       Delayed-Nu-Fission Rate              0.00137883 +/- 3.8999e-06
   Delayed Group 3
     Total Material
       Delayed-Nu-Fission Rate              0.00134379 +/- 3.746e-06
   Delayed Group 4
     Total Material
       Delayed-Nu-Fission Rate              0.00312032 +/- 8.50243e-06
   Delayed Group 5
     Total Material
       Delayed-Nu-Fission Rate              0.00139226 +/- 3.62702e-06
   Delayed Group 6
     Total Material
       Delayed-Nu-Fission Rate              0.000579335 +/- 1.51382e-06
 ============================>     TALLY 2     <============================

 Universe 317
   Delayed Group 1
     Total Material
       Decay Rate                           3.44311e-06 +/- 9.99219e-09
   Delayed Group 2
     Total Material
       Decay Rate                           4.49552e-05 +/- 1.27535e-07
   Delayed Group 3
     Total Material
       Decay Rate                           0.000162697 +/- 4.52792e-07
   Delayed Group 4
     Total Material
       Decay Rate                           0.000954257 +/- 2.58452e-06
   Delayed Group 5
     Total Material
       Decay Rate                           0.00119958 +/- 3.10601e-06
   Delayed Group 6
     Total Material
       Decay Rate                           0.00167659 +/- 4.3532e-06

I’m not sure what to suggest other than perhaps trying to upgrade your version of OpenMC and see if that fixes the problem. I don’t recall anything that changed between 0.13.0 and 0.13.2 that would have affected this but I very well may be forgetting some bug fixes!

1 Like
3

Thank you very much dr.romano.
Actually when I did filter by U and Pu nuclides , every thing going OK. and this what I need.

decay_rate.nuclides = [‘U234’,‘U235’,‘U236’,‘U238’,‘U239’,‘U240’ ,‘Pu239’,‘Pu240’,‘Pu241’,‘Pu242’]

thank you again for your answer.