Hello!
Ive been working on using OpenDeplete with openMC, and I’ve been getting an interesting error on the second burn step.
It is as follows.
====================> K EIGENVALUE SIMULATION <====================
Bat./Gen. k Entropy Average k
========= ======== ======== ====================
ERROR: No fission sites banked on processor 0
ERROR STOP
Increasing the number of particles form 10000 to 1000000 didn’t help, and there aren’t any geometry errors according to the openMC debug.
Any help would be greatly appreciated.
Thanks!
Jessica
Hi Jessica,
It is indeed strange that you are seeing this error even with a high number of particles per generation. What kind of machine are you running on? (i.e., OS, number of CPUs, MPI/OpenMP?) If you’re willing to share your input files/scripts, I can try to take a look to see what might be happening.
Thanks,
Paul
Im using a MacBook Pro (So OSX, quad-core, mpich and open-mpi)
Here’s the simplest input file I’ve been using, I adapted it from the pin cell example provided with OpenMC
Thank you!
Jessica
deck.py (5.51 KB)
Hi Jessica,
OpenDeplete was actually merged into OpenMC itself now as the openmc.deplete module. I would suggest trying to use the latest develop branch of OpenMC along with the functionality in openmc.deplete as there were definitely some changes between the original OpenDeplete and what got merged into OpenMC. The depletion capabilities haven’t been part of an OpenMC release yet which is why you’ll have to live on the bleeding edge if you want to try this functionality. Let me know if I can be of any help.
Best,
Paul