started conderc examlpe

examples/decay_heat_vs_time/decay_heat_vs_time.py

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+import openmc
+import openmc_depletion_plotter
+import openmc.deplete
+import math
+
+
+
+# makes a simple material from Silver
+my_material = openmc.Material() 
+my_material.add_element('Fe', 1, percent_type='ao')
+my_material.set_density('g/cm3', 10.49)
+
+sphere_radius = 100
+volume_of_sphere = (4/3) * math.pi * math.pow(sphere_radius, 3)
+my_material.volume = volume_of_sphere  # a volume is needed so openmc can find the number of atoms in the cell/material
+my_material.depletable = True  # depletable = True is needed to tell openmc to update the material with each time step
+
+materials = openmc.Materials([my_material])
+materials.export_to_xml()
+
+# GEOMETRY
+
+# surfaces
+sph1 = openmc.Sphere(r=sphere_radius, boundary_type='vacuum')
+
+# cells, makes a simple sphere cell
+shield_cell = openmc.Cell(region=-sph1)
+shield_cell.fill = my_material
+
+# sets the geometry to the universe that contains just the one cell
+universe = openmc.Universe(cells=[shield_cell])
+geometry = openmc.Geometry(universe)
+
+# creates a 14MeV neutron point source
+source = openmc.Source()
+source.space = openmc.stats.Point((0, 0, 0))
+source.angle = openmc.stats.Isotropic()
+source.energy = openmc.stats.Discrete([14e6], [1])
+source.particles = 'neutron'
+
+# SETTINGS
+
+# Instantiate a Settings object
+settings = openmc.Settings()
+settings.batches = 2
+settings.inactive = 0
+settings.particles = 10000
+settings.source = source
+settings.run_mode = 'fixed source'
+
+model = openmc.model.Model(geometry, materials, settings)
+
+operator = openmc.deplete.CoupledOperator(
+    model=model,
+    normalization_mode="source-rate",  # set for fixed source simulation, otherwise defaults to fission simulation
+    dilute_initial=0,  # set to zero to avoid adding small amounts of isotopes, defaults to adding small amounts of fissionable isotopes
+    reduce_chain=True,  # reduced to only the isotopes present in depletable materials and their possible progeny
+    reduce_chain_level=5,
+)
+
+# We define timesteps together with the source rate to make it clearer
+timesteps_and_source_rates = [
+    (5*60, 1e20),
+    (35, 0),
+    (15, 0),
+    (15, 0),
+    (16, 0),
+    (15, 0),
+    (26, 0),
+    (36, 0),
+    (36, 0),
+    (52, 0),
+    (66, 0),
+    (67, 0),
+    (97, 0),
+    (123, 0),
+    (123, 0),
+    (184, 0),
+    (246, 0),
+    (247, 0),
+    (246, 0),
+    (427, 0),
+    (607, 0),
+    (606, 0),
+]
+
+# Uses list Python comprehension to get the timesteps and source_rates separately
+timesteps = [item[0] for item in timesteps_and_source_rates]
+source_rates = [item[1] for item in timesteps_and_source_rates]
+
+integrator = openmc.deplete.PredictorIntegrator(
+    operator=operator,
+    timesteps=timesteps,
+    source_rates=source_rates,
+    timestep_units = 's'
+)
+
+integrator.integrate()
+
+results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
+
+plot = results.plot_decay_heat_vs_time(
+    x_scale='log',
+    y_scale='log',
+    excluded_material=my_material
+)
+plot.show()