Loading material from Depletion Previous Results using .h5 or Material.xml

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1

Hello, OpenMC expert.
My OpenMC project is to make the density of coolant converged in every depletion steps.

Here is how my program work.

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So, when the density is not converged, I use the old depletion_results.h5 file to simulation the same time step again. After the density converged I save the new density to Material.xml file.

So, I was wonder about material using in OpenMC depletion.
I found that in openmc.deplete prev_results may pull the material from depletion_results.h5.
openmc.deplete.abc — OpenMC Documentation

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This is the depletion command to use prev_reults
r = openmc.deplete.ResultsList.from_hdf5('depletion_results.h5')
operator = openmc.deplete.Operator(stacktest0, settings_file,"./chain_casl_pwr.xml", prev_results=r)

Then I don’t know how OpenMC prev_results actually works. I have thought 2 way.

  1. When having Material.xml in the directory and when it use prev_results the OpenMC will use Material.xml
  2. OpenMC will use material from depletion_results.h5 for next burnup.

Thank you.

1 Like
2

I Figure out that previous_result option use the result from depletion.h5 (not material.xml) by changing the the temperature before continue running, Is there any way to edit the density/compostion of the material in hdf5 before reume the calculation using previous_result option.

So I can update the material in my multiphysic loop calculation with out having to run at 0 everytime like
0 → 2 Mwd/kg , stop and update the composition xml then have to run at 2 again as 0 Mwd/kg
2 (0) → 3 (1) Mwd/kg

or else update it via new material .xml ?
Thank you

1 Like