Depletion not working

User Support
1

Hello. I am using OpenMC under Ubuntu 20.04. I successfully used OpenMc for Keff type calculations for criticality, rod worth, temperature reactivity, etc. I am trying to get the depletion module to work and I am having difficulty. I attempted to replicate the deplete example provided on the openmc site, using the code shown below. All statements up to the “integrator.integrate()” statement complete. The integrate module just seems to hang - CPU utilization initially peak s (99% of CPU resource to this task), then drops to zero, and I get a dialog asking “Your program is still running! Do you want to kill it?” without a control-C or other process kill request. I tried adding the (output=True) variable to the integrate module, but that generates an error that output is not a recognized variable. Any help would be appreciated.

import math
import openmc

fuel = openmc.Material(name=“uo2”)
fuel.add_element(“U”,1,percent_type=“ao”, enrichment = 4.25)
fuel.add_element(“O”,2)
fuel.set_density(“g/cc”,10.4)

clad = openmc.Material(name=“clad”)
clad.add_element(“Zr”,1)
clad.set_density(“g/cc”, 6)

water = openmc.Material(name=“water”)
water.add_element(“O”,1)
water.add_element(“H”,2)
water.set_density(“g/cc”,1.0)
water.add_s_alpha_beta(“c_H_in_H2O”)

materials = openmc.Materials([fuel, clad, water])
materials.cross_sections=“/home/brian/OpenMC_data/NuclearData/lib80x_hdf5/cross_sections.xml”

radii=[0.42,0.45]

pin_surfaces = [openmc.ZCylinder(r=r) for r in radii]
pin_univ = openmc.model.pin(pin_surfaces, materials)

bound_box = openmc.rectangular_prism(1.24,1.24, boundary_type=“reflective”)
root_cell = openmc.Cell(fill = pin_univ, region = bound_box)
geometry = openmc.Geometry([root_cell])

#geometry.root_universe.plot()

settings = openmc.Settings()
settings.particles = 1000
settings.inactive = 10
settings.batches = 50

fuel.volume = math.pi*radii[0]**2

import openmc.deplete

chain = openmc.deplete.Chain.from_xml(“chain_simple.xml”)
print(chain.nuclide_dict)

model = openmc.Model(geometry=geometry,materials=materials, settings=settings)
operator = openmc.deplete.Operator(model,“chain_simple.xml”)

print(“made it”)
power = 174

time_steps = [30] * 6

integrator = openmc.deplete.PredictorIntegrator(operator, time_steps, power, timestep_units = ‘d’)
print(“made #2”)
integrator.integrate(output=True)

2

Hi @Brian729,

I’m happy to help, but I need more information. Can you tell do the following?

  • Report your OpenMC version (run openmc -v in your shell)
  • Is this a python script or a jupyter notebook? In either case, try running using [pdb](https://docs.python.org/3/library/pdb.html) to see if you can learn more about what’s going on.
  • Run the test suite and post the entire output in a gist