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added xml for nuc data
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shimwell committed Jun 6, 2023
1 parent 9750c8f commit 2671c4a
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Showing 6 changed files with 15,863 additions and 5 deletions.
2 changes: 1 addition & 1 deletion pyproject.toml
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Expand Up @@ -34,7 +34,7 @@ write_to = "src/openmc_depletion_plotter/_version.py"

[project.optional-dependencies]
tests = [
"pytest"
"pytest",
]

[project.scripts]
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15,159 changes: 15,159 additions & 0 deletions tests/chain-nndc-b7.1.xml

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693 changes: 693 additions & 0 deletions tests/cross_sections.xml

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11 changes: 7 additions & 4 deletions tests/test_plots.py
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Expand Up @@ -3,7 +3,10 @@
import plotly
import openmc.deplete
import math
from pathlib import Path

openmc.config['cross_sections'] = Path(__file__).parent / 'cross_sections.xml'
openmc.config['chain_file'] = Path(__file__).parent / 'chain-nndc-b7.1.xml'

#TODO plot
# openmc.deplete.PredictorIntegrator plot_pulse_schedule
Expand All @@ -13,8 +16,8 @@

def test_default_isotope_charts():
my_mat = openmc.Material()
my_mat.add_element("Fe", 1)
my_mat.add_nuclide("Co60", 1)
my_mat.add_nuclide("Fe56", 1)
my_mat.add_nuclide("H1", 1)
my_mat.set_density('g/cm3', 1)
my_mat.volume = 1

Expand All @@ -27,9 +30,9 @@ def test_default_isotope_charts():

def test_default_time_plots():

# makes a simple material from Silver
# makes a simple material
my_material = openmc.Material()
my_material.add_element('Ag', 1, percent_type='ao')
my_material.add_nuclide('Fe56', 1, percent_type='ao')
my_material.set_density('g/cm3', 10.49)

sphere_radius = 100
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3 changes: 3 additions & 0 deletions tests/test_python_api.py
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Expand Up @@ -5,7 +5,10 @@
from openmc_depletion_plotter import get_nuclide_atoms_from_materials
from openmc_depletion_plotter import get_decay_heat_from_materials
import openmc
from pathlib import Path

openmc.config['cross_sections'] = Path(__file__).parent / 'cross_sections.xml'
openmc.config['chain_file'] = Path(__file__).parent / 'chain-nndc-b7.1.xml'

def test_find_nuclides_iron():

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