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db426b66ca
Co-authored-by: GuySten <guyste@post.bgu.ac.il> Co-authored-by: GuySten <62616591+GuySten@users.noreply.github.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
89 lines
3 KiB
Python
89 lines
3 KiB
Python
from pathlib import Path
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import openmc.deplete
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import numpy as np
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import pytest
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def test_deplete_decay_products(run_in_tmpdir):
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# Create chain file with H1, He4, and Li5
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with open('test_chain.xml', 'w') as chain_file:
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chain_file.write("""
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<depletion_chain>
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<nuclide name="H1" reactions="0">
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</nuclide>
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<nuclide name="He4" reactions="0"/>
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<nuclide name="Li5" half_life="3.06868e-22" decay_modes="1" decay_energy="1965000.0" reactions="0">
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<decay type="alpha" target="H1" branching_ratio="1.0"/>
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</nuclide>
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</depletion_chain>
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""")
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# Create MicroXS object with no cross sections
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micro_xs = openmc.deplete.MicroXS(np.empty((0, 0, 0)), [], [])
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# Create depletion operator with no reactions
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op = openmc.deplete.IndependentOperator.from_nuclides(
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volume=1.0,
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nuclides={'Li5': 1.0},
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flux=0.0,
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micro_xs=micro_xs,
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chain_file='test_chain.xml',
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normalization_mode='source-rate'
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)
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# Create time-integrator and integrate
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integrator = openmc.deplete.PredictorIntegrator(
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op, timesteps=[1.0], source_rates=[0.0], timestep_units='d'
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)
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integrator.integrate(final_step=False)
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# Get concentration of H1 and He4
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results = openmc.deplete.Results('depletion_results.h5')
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mat_id = op.materials[0].id
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_, h1 = results.get_atoms(f"{mat_id}", "H1")
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_, he4 = results.get_atoms(f"{mat_id}", "He4")
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# Since we started with 1e24 atoms of Li5, we should have 1e24 atoms of both
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# H1 and He4
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assert h1[1] == pytest.approx(1e24)
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assert he4[1] == pytest.approx(1e24)
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def test_deplete_decay_step_fissionable(run_in_tmpdir):
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"""Ensures that power is not computed in zero power cases with
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fissionable material present. This tests decay calculations without
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power, although this specific example does not exhibit any decay.
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Proves github issue #2963 is fixed
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"""
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# Set up a pure decay operator
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micro_xs = openmc.deplete.MicroXS(np.empty((0, 0, 0)), [], [])
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mat = openmc.Material()
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mat.name = 'I do not decay.'
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mat.add_nuclide('U238', 1.0, 'ao')
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mat.volume = 10.0
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mat.set_density('g/cc', 1.0)
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original_atoms = mat.get_nuclide_atoms()['U238']
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mats = openmc.Materials([mat])
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op = openmc.deplete.IndependentOperator(
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mats, [1.0], [micro_xs], Path(__file__).parents[1] / "chain_simple.xml")
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# Create time integrator and integrate
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integrator = openmc.deplete.PredictorIntegrator(
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op, [1.0], power=[0.0], timestep_units='s'
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)
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integrator.integrate()
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# Get concentration of U238. It should be unchanged since this chain has no U238 decay.
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results = openmc.deplete.Results('depletion_results.h5')
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_, u238 = results.get_atoms(f"{mat.id}", "U238")
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assert u238[1] == pytest.approx(original_atoms)
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# Check that material name is preserved in depletion results
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step_result = results[0]
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mat_from_results = step_result.get_material(f"{mat.id}")
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assert mat_from_results.name == 'I do not decay.'
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