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Fix deplete imports

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This commit is contained in:
Paul Romano 2018-02-09 14:01:59 -06:00
parent f8764416d2
commit 37f552a5dc
24 changed files with 141 additions and 146 deletions
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6
openmc/deplete/__init__.py
View file

@ -1,8 +1,8 @@
"""
OpenDeplete
===========
openmc.deplete
==============
A simple depletion front-end tool.
A depletion front-end tool.
"""
from .dummy_comm import DummyCommunicator

18
openmc/deplete/atom_number.py
View file

@ -7,7 +7,7 @@ import numpy as np
class AtomNumber(object):
""" AtomNumber module.
"""AtomNumber module.
An ndarray to store atom densities with string, integer, or slice indexing.
@ -71,7 +71,7 @@ class AtomNumber(object):
self._burn_mat_list = None
def __getitem__(self, pos):
""" Retrieves total atom number from AtomNumber.
"""Retrieves total atom number from AtomNumber.
Parameters
----------
@ -95,7 +95,7 @@ class AtomNumber(object):
return self.number[mat, nuc]
def __setitem__(self, pos, val):
""" Sets total atom number into AtomNumber.
"""Sets total atom number into AtomNumber.
Parameters
----------
@ -116,7 +116,7 @@ class AtomNumber(object):
self.number[mat, nuc] = val
def get_atom_density(self, mat, nuc):
""" Accesses atom density instead of total number.
"""Accesses atom density instead of total number.
Parameters
----------
@ -139,7 +139,7 @@ class AtomNumber(object):
return self[mat, nuc] / self.volume[mat]
def set_atom_density(self, mat, nuc, val):
""" Sets atom density instead of total number.
"""Sets atom density instead of total number.
Parameters
----------
@ -159,7 +159,7 @@ class AtomNumber(object):
self[mat, nuc] = val * self.volume[mat]
def get_mat_slice(self, mat):
""" Gets atom quantity indexed by mats for all burned nuclides
"""Gets atom quantity indexed by mats for all burned nuclides
Parameters
----------
@ -178,7 +178,7 @@ class AtomNumber(object):
return self[mat, 0:self.n_nuc_burn]
def set_mat_slice(self, mat, val):
""" Sets atom quantity indexed by mats for all burned nuclides
"""Sets atom quantity indexed by mats for all burned nuclides
Parameters
----------
@ -205,7 +205,7 @@ class AtomNumber(object):
@property
def burn_nuc_list(self):
""" burn_nuc_list : list of str
"""burn_nuc_list : list of str
A list of all nuclide material names. Used for sorting the simulation.
"""
@ -221,7 +221,7 @@ class AtomNumber(object):
@property
def burn_mat_list(self):
""" burn_mat_list : list of str
"""burn_mat_list : list of str
A list of all burning material names. Used for sorting the simulation.
"""

18
openmc/deplete/depletion_chain.py
View file

@ -11,9 +11,6 @@ import math
import re
import os
from tqdm import tqdm
import scipy.sparse as sp
import openmc.data
# Try to use lxml if it is available. It preserves the order of attributes and
# provides a pretty-printer by default. If not available, use OpenMC function to
# pretty print.
@ -22,9 +19,12 @@ try:
_have_lxml = True
except ImportError:
import xml.etree.ElementTree as ET
from openmc.clean_xml import clean_xml_indentation
_have_lxml = False
from tqdm import tqdm
import scipy.sparse as sp
import openmc.data
from openmc.clean_xml import clean_xml_indentation
from .nuclide import Nuclide, DecayTuple, ReactionTuple
@ -109,7 +109,7 @@ def replace_missing(product, decay_data):
class DepletionChain(object):
""" The DepletionChain class.
"""The DepletionChain class.
This class contains a full representation of a depletion chain.
@ -334,7 +334,7 @@ class DepletionChain(object):
# Load XML tree
try:
root = ET.parse(filename)
except:
except Exception:
if filename is None:
print("No chain specified, either manually or in environment variable OPENDEPLETE_CHAIN.")
else:
@ -374,11 +374,11 @@ class DepletionChain(object):
if _have_lxml:
tree.write(filename, encoding='utf-8', pretty_print=True)
else:
clean_xml_indentation(root_elem, spaces_per_level=2)
clean_xml_indentation(root_elem)
tree.write(filename, encoding='utf-8')
def form_matrix(self, rates):
""" Forms depletion matrix.
"""Forms depletion matrix.
Parameters
----------
@ -457,7 +457,7 @@ class DepletionChain(object):
return matrix_dok.tocsr()
def nuc_by_ind(self, ind):
""" Extracts nuclides from the list by dictionary key.
"""Extracts nuclides from the list by dictionary key.
Parameters
----------

14
openmc/deplete/function.py
View file

@ -6,8 +6,9 @@ to run a full depletion simulation.
from abc import ABCMeta, abstractmethod
class Settings(object):
""" The Settings class.
"""The Settings class.
Contains all parameters necessary for the integrator.
@ -24,8 +25,9 @@ class Settings(object):
self.dt_vec = None
self.output_dir = None
class Operator(metaclass=ABCMeta):
""" The Operator metaclass.
"""The Operator metaclass.
This defines all functions that the integrator needs to operate.
@ -40,7 +42,7 @@ class Operator(metaclass=ABCMeta):
@abstractmethod
def initial_condition(self):
""" Performs final setup and returns initial condition.
"""Performs final setup and returns initial condition.
Returns
-------
@ -52,7 +54,7 @@ class Operator(metaclass=ABCMeta):
@abstractmethod
def eval(self, vec, print_out=True):
""" Runs a simulation.
"""Runs a simulation.
Parameters
----------
@ -75,7 +77,7 @@ class Operator(metaclass=ABCMeta):
@abstractmethod
def get_results_info(self):
""" Returns volume list, cell lists, and nuc lists.
"""Returns volume list, cell lists, and nuc lists.
Returns
-------
@ -93,7 +95,7 @@ class Operator(metaclass=ABCMeta):
@abstractmethod
def form_matrix(self, y, mat):
""" Forms the f(y) matrix in y' = f(y)y.
"""Forms the f(y) matrix in y' = f(y)y.
Nominally a depletion matrix, this is abstracted on the off chance
that the function f has nothing to do with depletion at all.

3
openmc/deplete/integrator/save_results.py
View file

@ -1,7 +1,8 @@
""" Generic result saving code for integrators.
"""
from opendeplete.results import Results, write_results
from ..results import Results, write_results
def save_results(op, x, rates, eigvls, seeds, t, step_ind):
""" Creates and writes results to disk

52
openmc/deplete/openmc_wrapper.py
View file

@ -1,6 +1,6 @@
""" The OpenMC wrapper module.
"""The OpenMC wrapper module.
This module implements the OpenDeplete -> OpenMC linkage.
This module implements the depletion -> OpenMC linkage.
"""
import copy
@ -14,14 +14,13 @@ try:
_have_lxml = True
except ImportError:
import xml.etree.ElementTree as ET
from openmc.clean_xml import clean_xml_indentation
_have_lxml = False
import h5py
import numpy as np
import openmc
import openmc.capi
from . import comm
from .atom_number import AtomNumber
from .depletion_chain import DepletionChain
@ -194,7 +193,7 @@ class OpenMCOperator(Operator):
# Clear out OpenMC, create task lists, distribute
if comm.rank == 0:
clean_up_openmc()
openmc.reset_auto_ids()
mat_burn_list, mat_not_burn_list, volume, self.mat_tally_ind, \
nuc_dict = self.extract_mat_ids()
else:
@ -224,7 +223,7 @@ class OpenMCOperator(Operator):
openmc.capi.finalize()
def extract_mat_ids(self):
""" Extracts materials and assigns them to processes.
"""Extracts materials and assigns them to processes.
Returns
-------
@ -308,7 +307,7 @@ class OpenMCOperator(Operator):
return mat_burn_lists, mat_not_burn_lists, volume, mat_tally_ind, nuc_dict
def extract_number(self, mat_burn, mat_not_burn, volume, nuc_dict):
""" Construct self.number read from geometry
"""Construct self.number read from geometry
Parameters
----------
@ -356,7 +355,7 @@ class OpenMCOperator(Operator):
self.set_number_from_mat(mat)
def set_number_from_mat(self, mat):
""" Extracts material and number densities from openmc.Material
"""Extracts material and number densities from openmc.Material
Parameters
----------
@ -369,12 +368,11 @@ class OpenMCOperator(Operator):
nuc_dens = mat.get_nuclide_atom_densities()
for nuclide in nuc_dens:
name = nuclide.name
number = nuc_dens[nuclide][1] * 1.0e24
self.number.set_atom_density(mat_id, name, number)
self.number.set_atom_density(mat_id, nuclide, number)
def initialize_reaction_rates(self):
""" Create reaction rates object. """
"""Create reaction rates object. """
self.reaction_rates = ReactionRates(
self.burn_mat_to_ind,
self.burn_nuc_to_ind,
@ -383,7 +381,7 @@ class OpenMCOperator(Operator):
self.chain.nuc_to_react_ind = self.burn_nuc_to_ind
def eval(self, vec, print_out=True):
""" Runs a simulation.
"""Runs a simulation.
Parameters
----------
@ -405,7 +403,7 @@ class OpenMCOperator(Operator):
"""
# Prevent OpenMC from complaining about re-creating tallies
clean_up_openmc()
openmc.reset_auto_ids()
# Update status
self.set_density(vec)
@ -435,7 +433,7 @@ class OpenMCOperator(Operator):
return k, copy.deepcopy(self.reaction_rates), self.seed
def form_matrix(self, y, mat):
""" Forms the depletion matrix.
"""Forms the depletion matrix.
Parameters
----------
@ -453,7 +451,7 @@ class OpenMCOperator(Operator):
return copy.deepcopy(self.chain.form_matrix(y[mat, :, :]))
def initial_condition(self):
""" Performs final setup and returns initial condition.
"""Performs final setup and returns initial condition.
Returns
-------
@ -513,7 +511,7 @@ class OpenMCOperator(Operator):
mat_internal.set_densities(nuclides, densities)
def generate_materials_xml(self):
""" Creates materials.xml from self.number.
"""Creates materials.xml from self.number.
Due to uncertainty with how MPI interacts with OpenMC API, this
constructs the XML manually. The long term goal is to do this
@ -531,7 +529,7 @@ class OpenMCOperator(Operator):
materials.export_to_xml()
def generate_settings_xml(self):
""" Generates settings.xml.
"""Generates settings.xml.
This function creates settings.xml using the value of the settings
variable.
@ -625,7 +623,7 @@ class OpenMCOperator(Operator):
tally_dep.filters = [mat_filter]
def total_density_list(self):
""" Returns a list of total density lists.
"""Returns a list of total density lists.
This list is in the exact same order as depletion_matrix_list, so that
matrix exponentiation can be done easily.
@ -641,7 +639,7 @@ class OpenMCOperator(Operator):
return total_density
def set_density(self, total_density):
""" Sets density.
"""Sets density.
Sets the density in the exact same order as total_density_list outputs,
allowing for internal consistency
@ -657,7 +655,7 @@ class OpenMCOperator(Operator):
self.number.set_mat_slice(i, total_density[i])
def unpack_tallies_and_normalize(self):
""" Unpack tallies from OpenMC
"""Unpack tallies from OpenMC
This function reads the tallies generated by OpenMC (from the tally.xml
file generated in generate_tally_xml) normalizes them so that the total
@ -754,7 +752,7 @@ class OpenMCOperator(Operator):
return k_combined
def load_participating(self):
""" Loads a cross_sections.xml file to find participating nuclides.
"""Loads a cross_sections.xml file to find participating nuclides.
This allows for nuclides that are important in the decay chain but not
important neutronically, or have no cross section data.
@ -772,7 +770,7 @@ class OpenMCOperator(Operator):
try:
tree = ET.parse(filename)
except:
except Exception:
if filename is None:
msg = "No cross_sections.xml specified in materials."
else:
@ -802,7 +800,7 @@ class OpenMCOperator(Operator):
return len(self.chain.nuclides)
def get_results_info(self):
""" Returns volume list, cell lists, and nuc lists.
"""Returns volume list, cell lists, and nuc lists.
Returns
-------
@ -829,8 +827,10 @@ class OpenMCOperator(Operator):
return volume, nuc_list, burn_list, self.mat_tally_ind
def density_to_mat(dens_dict):
""" Generates an OpenMC material from a cell ID and self.number_density.
"""Generates an OpenMC material from a cell ID and self.number_density.
Parameters
----------
m_id : int
@ -847,7 +847,3 @@ def density_to_mat(dens_dict):
mat.set_density('sum')
return mat
def clean_up_openmc():
""" Resets all automatic indexing in OpenMC, as these get in the way. """
openmc.reset_auto_ids()

6
openmc/deplete/reaction_rates.py
View file

@ -7,7 +7,7 @@ import numpy as np
class ReactionRates(object):
""" ReactionRates class.
"""ReactionRates class.
An ndarray to store reaction rates with string, integer, or slice indexing.
@ -47,7 +47,7 @@ class ReactionRates(object):
self.rates = np.zeros((self.n_mat, self.n_nuc, self.n_react))
def __getitem__(self, pos):
""" Retrieves an item from reaction_rates.
"""Retrieves an item from reaction_rates.
Parameters
----------
@ -74,7 +74,7 @@ class ReactionRates(object):
return self.rates[mat, nuc, react]
def __setitem__(self, pos, val):
""" Sets an item from reaction_rates.
"""Sets an item from reaction_rates.
Parameters
----------

23
openmc/deplete/results.py
View file

@ -1,4 +1,4 @@
""" The results module.
"""The results module.
Contains results generation and saving capabilities.
"""
@ -14,8 +14,9 @@ from .reaction_rates import ReactionRates
RESULTS_VERSION = 2
class Results(object):
""" Contains output of opendeplete.
"""Contains output of opendeplete.
Attributes
----------
@ -62,7 +63,7 @@ class Results(object):
self.data = None
def allocate(self, volume, nuc_list, burn_list, full_burn_dict, stages):
""" Allocates memory of Results.
"""Allocates memory of Results.
Parameters
----------
@ -113,7 +114,7 @@ class Results(object):
return self.data.shape[0]
def __getitem__(self, pos):
""" Retrieves an item from results.
"""Retrieves an item from results.
Parameters
----------
@ -137,7 +138,7 @@ class Results(object):
return self.data[stage, mat, nuc]
def __setitem__(self, pos, val):
""" Sets an item from results.
"""Sets an item from results.
Parameters
----------
@ -159,7 +160,7 @@ class Results(object):
self.data[stage, mat, nuc] = val
def create_hdf5(self, handle):
""" Creates file structure for a blank HDF5 file.
"""Creates file structure for a blank HDF5 file.
Parameters
----------
@ -232,7 +233,7 @@ class Results(object):
handle.create_dataset("time", (1, 2), maxshape=(None, 2), dtype='float64')
def to_hdf5(self, handle, index):
""" Converts results object into an hdf5 object.
"""Converts results object into an hdf5 object.
Parameters
----------
@ -302,7 +303,7 @@ class Results(object):
time_dset[index, :] = self.time
def from_hdf5(self, handle, index):
""" Loads results object from HDF5.
"""Loads results object from HDF5.
Parameters
----------
@ -360,7 +361,7 @@ class Results(object):
def get_dict(number):
""" Given an operator nested dictionary, output indexing dictionaries.
"""Given an operator nested dictionary, output indexing dictionaries.
These indexing dictionaries map mat IDs and nuclide names to indices
inside of Results.data.
@ -394,7 +395,7 @@ def get_dict(number):
def write_results(result, filename, index):
""" Outputs result to an .hdf5 file.
"""Outputs result to an .hdf5 file.
Parameters
----------
@ -418,7 +419,7 @@ def write_results(result, filename, index):
def read_results(filename):
""" Reads out a list of results objects from an hdf5 file.
"""Reads out a list of results objects from an hdf5 file.
Parameters
----------

10
openmc/deplete/utilities.py
View file

@ -1,4 +1,4 @@
""" The utilities module.
"""The utilities module.
Contains functions that can be used to post-process objects that come out of
the results module.
@ -6,8 +6,9 @@ the results module.
import numpy as np
def evaluate_single_nuclide(results, cell, nuc):
""" Evaluates a single nuclide in a single cell from a results list.
"""Evaluates a single nuclide in a single cell from a results list.
Parameters
----------
@ -38,7 +39,7 @@ def evaluate_single_nuclide(results, cell, nuc):
return time, concentration
def evaluate_reaction_rate(results, cell, nuc, rxn):
""" Evaluates a single nuclide reaction rate in a single cell from a results list.
"""Evaluates a single nuclide reaction rate in a single cell from a results list.
Parameters
----------
@ -69,8 +70,9 @@ def evaluate_reaction_rate(results, cell, nuc, rxn):
return time, rate
def evaluate_eigenvalue(results):
""" Evaluates the eigenvalue from a results list.
"""Evaluates the eigenvalue from a results list.
Parameters
----------

3
scripts/example_geometry.py
View file

@ -9,8 +9,7 @@ import math
import numpy as np
import openmc
from opendeplete import density_to_mat
from openmc.deplete import density_to_mat
def generate_initial_number_density():

7
scripts/example_plot.py
View file

@ -1,11 +1,8 @@
"""An example file showing how to plot data from a simulation."""
import matplotlib.pyplot as plt
from opendeplete import read_results, \
evaluate_single_nuclide, \
evaluate_reaction_rate, \
evaluate_eigenvalue
from openmc.deplete import (read_results, evaluate_single_nuclide,
evaluate_reaction_rate, evaluate_eigenvalue)
# Set variables for where the data is, and what we want to read out.
result_folder = "test"

8
scripts/example_run.py
View file

@ -1,7 +1,7 @@
"""An example file showing how to run a simulation."""
import numpy as np
import opendeplete
import openmc.deplete
import example_geometry
@ -16,7 +16,7 @@ N = np.floor(dt2/dt1)
dt = np.repeat([dt1], N)
# Create settings variable
settings = opendeplete.OpenMCSettings()
settings = openmc.deplete.OpenMCSettings()
settings.openmc_call = "openmc"
# An example for mpiexec:
@ -33,7 +33,7 @@ settings.power = 2.337e15*4*joule_per_mev # MeV/second cm from CASMO
settings.dt_vec = dt
settings.output_dir = 'test'
op = opendeplete.OpenMCOperator(geometry, settings)
op = openmc.deplete.OpenMCOperator(geometry, settings)
# Perform simulation using the MCNPX/MCNP6 algorithm
opendeplete.integrator.cecm(op)
openmc.deplete.integrator.cecm(op)

4
scripts/make_chain.py
View file

@ -6,7 +6,7 @@ from zipfile import ZipFile
import requests
from tqdm import tqdm
import opendeplete
import openmc.deplete
urls = [
@ -52,7 +52,7 @@ def main():
nfy_files = glob.glob(os.path.join('nfy', '*.endf'))
neutron_files = glob.glob(os.path.join('neutrons', '*.endf'))
chain = opendeplete.DepletionChain.from_endf(decay_files, nfy_files, neutron_files)
chain = openmc.deplete.DepletionChain.from_endf(decay_files, nfy_files, neutron_files)
chain.xml_write('chain_endfb71.xml')

22
tests/deplete_tests/dummy_geometry.py
View file

@ -1,16 +1,11 @@
""" The OpenMC wrapper module.
This module implements the OpenDeplete -> OpenMC linkage.
"""
import numpy as np
import scipy.sparse as sp
from openmc.deplete.reaction_rates import ReactionRates
from openmc.deplete.function import Operator
from opendeplete.reaction_rates import ReactionRates
from opendeplete.function import Operator
class DummyGeometry(Operator):
""" This is a dummy geometry class with no statistical uncertainty.
"""This is a dummy geometry class with no statistical uncertainty.
y_1' = sin(y_2) y_1 + cos(y_1) y_2
y_2' = -cos(y_2) y_1 + sin(y_1) y_2
@ -24,14 +19,14 @@ class DummyGeometry(Operator):
"""
def __init__(self, settings):
Operator.__init__(self, settings)
super().__init__(settings)
@property
def chain(self):
return self
def eval(self, vec, print_out=False):
""" Evaluates F(y)
"""Evaluates F(y)
Parameters
----------
@ -60,11 +55,10 @@ class DummyGeometry(Operator):
reaction_rates[0, 1, 0] = vec[0][1]
# Create a fake rates object
return 0.0, reaction_rates, 0
def form_matrix(self, rates):
""" Forms the f(y) matrix in y' = f(y)y.
"""Forms the f(y) matrix in y' = f(y)y.
Nominally a depletion matrix, this is abstracted on the off chance
that the function f has nothing to do with depletion at all.
@ -137,7 +131,7 @@ class DummyGeometry(Operator):
return ReactionRates(cell_to_ind, nuc_to_ind, react_to_ind)
def initial_condition(self):
""" Returns initial vector.
"""Returns initial vector.
Returns
-------
@ -148,7 +142,7 @@ class DummyGeometry(Operator):
return [np.array((1.0, 1.0))]
def get_results_info(self):
""" Returns volume list, cell lists, and nuc lists.
"""Returns volume list, cell lists, and nuc lists.
Returns
-------

12
tests/deplete_tests/test_atom_number.py
View file

@ -3,11 +3,11 @@
import unittest
import numpy as np
from openmc.deplete import atom_number
from opendeplete import atom_number
class TestAtomNumber(unittest.TestCase):
""" Tests for the AtomNumber class. """
"""Tests for the AtomNumber class."""
def test_indexing(self):
"""Tests the __getitem__ and __setitem__ routines simultaneously."""
@ -41,7 +41,7 @@ class TestAtomNumber(unittest.TestCase):
self.assertEqual(number["10000", "U238"], 5.0)
def test_n_mat(self):
""" Test number of materials property. """
"""Test number of materials property. """
mat_to_ind = {"10000" : 0, "10001" : 1}
nuc_to_ind = {"U238" : 0, "U235" : 1, "Gd157" : 2}
volume = {"10000" : 0.38, "10001" : 0.21}
@ -51,7 +51,7 @@ class TestAtomNumber(unittest.TestCase):
self.assertEqual(number.n_mat, 2)
def test_n_nuc(self):
""" Test number of nuclides property. """
"""Test number of nuclides property."""
mat_to_ind = {"10000" : 0, "10001" : 1}
nuc_to_ind = {"U238" : 0, "U235" : 1, "Gd157" : 2}
volume = {"10000" : 0.38, "10001" : 0.21}
@ -61,7 +61,7 @@ class TestAtomNumber(unittest.TestCase):
self.assertEqual(number.n_nuc, 3)
def test_burn_nuc_list(self):
""" Test the list of burned nuclides property """
"""Test the list of burned nuclides property"""
mat_to_ind = {"10000" : 0, "10001" : 1}
nuc_to_ind = {"U238" : 0, "U235" : 1, "Gd157" : 2}
volume = {"10000" : 0.38, "10001" : 0.21}
@ -71,7 +71,7 @@ class TestAtomNumber(unittest.TestCase):
self.assertEqual(number.burn_nuc_list, ["U238", "U235"])
def test_burn_mat_list(self):
""" Test the list of burned nuclides property """
"""Test the list of burned nuclides property"""
mat_to_ind = {"10000" : 0, "10001" : 1, "10002" : 2}
nuc_to_ind = {"U238" : 0, "U235" : 1, "Gd157" : 2}
volume = {"10000" : 0.38, "10001" : 0.21}

16
tests/deplete_tests/test_cecm_regression.py
View file

@ -4,11 +4,11 @@ import os
import unittest
import numpy as np
import openmc.deplete
from openmc.deplete import results
from openmc.deplete import utilities
import opendeplete
from opendeplete import results
from opendeplete import utilities
import test.dummy_geometry as dummy_geometry
from . import dummy_geometry
class TestCECMRegression(unittest.TestCase):
@ -26,14 +26,14 @@ class TestCECMRegression(unittest.TestCase):
def test_cecm(self):
""" Integral regression test of integrator algorithm using CE/CM. """
settings = opendeplete.Settings()
settings = openmc.deplete.Settings()
settings.dt_vec = [0.75, 0.75]
settings.output_dir = self.results
op = dummy_geometry.DummyGeometry(settings)
# Perform simulation using the MCNPX/MCNP6 algorithm
opendeplete.cecm(op, print_out=False)
openmc.deplete.cecm(op, print_out=False)
# Load the files
res = results.read_results(settings.output_dir + "/results.h5")
@ -59,8 +59,8 @@ class TestCECMRegression(unittest.TestCase):
os.chdir(cls.cwd)
opendeplete.comm.barrier()
if opendeplete.comm.rank == 0:
openmc.deplete.comm.barrier()
if openmc.deplete.comm.rank == 0:
os.remove(os.path.join(cls.results, "results.h5"))
os.rmdir(cls.results)

2
tests/deplete_tests/test_cram.py
View file

@ -4,8 +4,8 @@ import unittest
import numpy as np
import scipy.sparse as sp
from openmc.deplete.integrator import CRAM16, CRAM48
from opendeplete.integrator import CRAM16, CRAM48
class TestCram(unittest.TestCase):
""" Tests for cram.py

3
tests/deplete_tests/test_depletion_chain.py
View file

@ -5,8 +5,7 @@ import os
import unittest
import numpy as np
from opendeplete import comm, depletion_chain, reaction_rates, nuclide
from openmc.deplete import comm, depletion_chain, reaction_rates, nuclide
class TestDepletionChain(unittest.TestCase):

22
tests/deplete_tests/test_full.py
View file

@ -2,13 +2,14 @@
import shutil
import unittest
from os.path import join, dirname
import numpy as np
import openmc.deplete
from openmc.deplete import results
from openmc.deplete import utilities
import opendeplete
from opendeplete import results
from opendeplete import utilities
import test.example_geometry as example_geometry
from . import example_geometry
class TestFull(unittest.TestCase):
@ -40,7 +41,7 @@ class TestFull(unittest.TestCase):
dt = np.repeat([dt1], N)
# Create settings variable
settings = opendeplete.OpenMCSettings()
settings = openmc.deplete.OpenMCSettings()
settings.chain_file = "chains/chain_simple.xml"
settings.openmc_call = "openmc"
@ -60,16 +61,17 @@ class TestFull(unittest.TestCase):
settings.dt_vec = dt
settings.output_dir = "test_full"
op = opendeplete.OpenMCOperator(geometry, settings)
op = openmc.deplete.OpenMCOperator(geometry, settings)
# Perform simulation using the predictor algorithm
opendeplete.integrator.predictor(op)
openmc.deplete.integrator.predictor(op)
# Load the files
res_test = results.read_results(settings.output_dir + "/results.h5")
# Load the reference
res_old = results.read_results("test/test_reference.h5")
filename = join(dirname(__file__), 'test_reference.h5')
res_old = results.read_results(filename)
# Assert same mats
for mat in res_old[0].mat_to_ind:
@ -110,8 +112,8 @@ class TestFull(unittest.TestCase):
def tearDown(self):
""" Clean up files"""
opendeplete.comm.barrier()
if opendeplete.comm.rank == 0:
openmc.deplete.comm.barrier()
if openmc.deplete.comm.rank == 0:
shutil.rmtree("test_full", ignore_errors=True)

3
tests/deplete_tests/test_integrator.py
View file

@ -6,8 +6,7 @@ import unittest
from unittest.mock import MagicMock
import numpy as np
from opendeplete import integrator, ReactionRates, results, comm
from openmc.deplete import integrator, ReactionRates, results, comm
class TestIntegrator(unittest.TestCase):

2
tests/deplete_tests/test_nuclide.py
View file

@ -3,7 +3,7 @@
import unittest
import xml.etree.ElementTree as ET
from opendeplete import nuclide
from openmc.deplete import nuclide
class TestNuclide(unittest.TestCase):

16
tests/deplete_tests/test_predictor_regression.py
View file

@ -4,11 +4,11 @@ import os
import unittest
import numpy as np
import openmc.deplete
from openmc.deplete import results
from openmc.deplete import utilities
import opendeplete
from opendeplete import results
from opendeplete import utilities
import test.dummy_geometry as dummy_geometry
from . import dummy_geometry
class TestPredictorRegression(unittest.TestCase):
""" Regression tests for opendeplete.integrator.predictor algorithm.
@ -25,14 +25,14 @@ class TestPredictorRegression(unittest.TestCase):
def test_predictor(self):
""" Integral regression test of integrator algorithm using CE/CM. """
settings = opendeplete.Settings()
settings = openmc.deplete.Settings()
settings.dt_vec = [0.75, 0.75]
settings.output_dir = self.results
op = dummy_geometry.DummyGeometry(settings)
# Perform simulation using the predictor algorithm
opendeplete.predictor(op, print_out=False)
openmc.deplete.predictor(op, print_out=False)
# Load the files
res = results.read_results(settings.output_dir + "/results.h5")
@ -58,8 +58,8 @@ class TestPredictorRegression(unittest.TestCase):
os.chdir(cls.cwd)
opendeplete.comm.barrier()
if opendeplete.comm.rank == 0:
openmc.deplete.comm.barrier()
if openmc.deplete.comm.rank == 0:
os.remove(os.path.join(cls.results, "results.h5"))
os.rmdir(cls.results)

2
tests/deplete_tests/test_reaction_rates.py
View file

@ -2,7 +2,7 @@
import unittest
from opendeplete import reaction_rates
from openmc.deplete import reaction_rates
class TestReactionRates(unittest.TestCase):

15
tests/deplete_tests/test_utilities.py
View file

@ -1,11 +1,11 @@
""" Full system test suite. """
import unittest
from os.path import join, dirname
import numpy as np
from opendeplete import results
from opendeplete import utilities
from openmc.deplete import results
from openmc.deplete import utilities
class TestUtilities(unittest.TestCase):
@ -19,7 +19,8 @@ class TestUtilities(unittest.TestCase):
"""
# Load the reference
res = results.read_results("test/test_reference.h5")
filename = join(dirname(__file__), 'test_reference.h5')
res = results.read_results(filename)
x, y = utilities.evaluate_single_nuclide(res, "1", "Xe135")
@ -35,7 +36,8 @@ class TestUtilities(unittest.TestCase):
"""
# Load the reference
res = results.read_results("test/test_reference.h5")
filename = join(dirname(__file__), 'test_reference.h5')
res = results.read_results(filename)
x, y = utilities.evaluate_reaction_rate(res, "1", "Xe135", "(n,gamma)")
@ -53,7 +55,8 @@ class TestUtilities(unittest.TestCase):
"""
# Load the reference
res = results.read_results("test/test_reference.h5")
filename = join(dirname(__file__), 'test_reference.h5')
res = results.read_results(filename)
x, y = utilities.evaluate_eigenvalue(res)