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Merge 851c20fa42 into 61c8a59cff

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Patrick Shriwise 2026-07-20 14:01:35 -05:00 • committed by GitHub
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54 changed files with 2139 additions and 122 deletions
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31
.github/workflows/ci.yml vendored
View file

@ -46,8 +46,6 @@ jobs:
python-version: ["3.12"]
mpi: [n, y]
omp: [n, y]
dagmc: [n]
libmesh: [n]
event: [n]
include:
@ -60,33 +58,26 @@ jobs:
- python-version: "3.14t"
omp: n
mpi: n
- dagmc: y
python-version: "3.12"
mpi: y
omp: y
- libmesh: y
python-version: "3.12"
mpi: y
omp: y
- libmesh: y
python-version: "3.12"
- python-version: "3.12"
omp: n
mpi: n
omp: y
umesh_libs: y
- event: y
python-version: "3.12"
omp: y
mpi: n
name: "Python ${{ matrix.python-version }} (omp=${{ matrix.omp }},
mpi=${{ matrix.mpi }}, dagmc=${{ matrix.dagmc }},
libmesh=${{ matrix.libmesh }}, event=${{ matrix.event }}"
mpi=${{ matrix.mpi }}, umesh_libs=${{ matrix.umesh_libs }},
event=${{ matrix.event }}"
env:
MPI: ${{ matrix.mpi }}
PHDF5: ${{ matrix.mpi }}
OMP: ${{ matrix.omp }}
DAGMC: ${{ matrix.dagmc }}
DAGMC: ${{ matrix.umesh_libs }}
XDG: ${{ matrix.umesh_libs }}
EVENT: ${{ matrix.event }}
LIBMESH: ${{ matrix.libmesh }}
LIBMESH: ${{ matrix.umesh_libs }}
NPY_DISABLE_CPU_FEATURES: "AVX512F AVX512_SKX"
OPENBLAS_NUM_THREADS: 1
PYTEST_ADDOPTS: --cov=openmc --cov-report=lcov:coverage-python.lcov
@ -146,6 +137,12 @@ jobs:
sudo update-alternatives --set mpirun /usr/bin/mpirun.mpich
sudo update-alternatives --set mpi-x86_64-linux-gnu /usr/include/x86_64-linux-gnu/mpich
- name: Optional apt dependencies for XDG
shell: bash
if: ${{ matrix.umesh_libs == 'y' }}
run: |
sudo apt install -y libembree-dev
- name: install
shell: bash
run: |

16
CMakeLists.txt
View file

@ -39,6 +39,7 @@ option(OPENMC_BUILD_TESTS "Build tests"
option(OPENMC_ENABLE_PROFILE "Compile with profiling flags" OFF)
option(OPENMC_ENABLE_COVERAGE "Compile with coverage analysis flags" OFF)
option(OPENMC_USE_DAGMC "Enable support for DAGMC (CAD) geometry" OFF)
option(OPENMC_USE_XDG "Enable support for XDG discretized CAD geometry" OFF)
option(OPENMC_USE_LIBMESH "Enable support for libMesh unstructured mesh tallies" OFF)
option(OPENMC_USE_MPI "Enable MPI" OFF)
option(OPENMC_USE_UWUW "Enable UWUW" OFF)
@ -156,6 +157,15 @@ if(OPENMC_USE_DAGMC)
endif()
endif()
#===============================================================================
# XDG Mesh and Geometry Support
#===============================================================================
if(OPENMC_USE_XDG)
find_package(XDG REQUIRED PATH_SUFFIXES lib/cmake)
message(STATUS "Found XDG: ${XDG_DIR} (version ${XDG_VERSION})")
endif()
#===============================================================================
# libMesh Unstructured Mesh Support
#===============================================================================
@ -428,6 +438,7 @@ list(APPEND libopenmc_SOURCES
src/string_utils.cpp
src/summary.cpp
src/surface.cpp
src/xdg.cpp
src/tallies/derivative.cpp
src/tallies/filter.cpp
src/tallies/filter_azimuthal.cpp
@ -544,6 +555,11 @@ elseif(OPENMC_USE_UWUW)
message(FATAL_ERROR "DAGMC must be enabled when UWUW is enabled.")
endif()
if(OPENMC_USE_XDG)
target_compile_definitions(libopenmc PRIVATE OPENMC_XDG_ENABLED)
target_link_libraries(libopenmc xdg::xdg)
endif()
if(OPENMC_USE_LIBMESH)
target_compile_definitions(libopenmc PRIVATE OPENMC_LIBMESH_ENABLED)
target_link_libraries(libopenmc PkgConfig::LIBMESH)

4
cmake/OpenMCConfig.cmake.in
View file

@ -26,6 +26,10 @@ if("@PNG_FOUND@")
find_dependency(PNG)
endif()
if(@OPENMC_USE_XDG@)
find_dependency(XDG REQUIRED HINTS @XDG_DIR@)
endif()
if(@OPENMC_USE_MPI@)
find_dependency(MPI REQUIRED)
endif()

34
include/openmc/mesh.h
View file

@ -771,6 +771,9 @@ public:
//! Get the library used for this unstructured mesh
virtual std::string library() const = 0;
//! Get the mesh filename
virtual const std::string& filename() const { return filename_; }
// Data members
bool output_ {
true}; //!< Write tallies onto the unstructured mesh at the end of a run
@ -797,7 +800,36 @@ protected:
//! \param[in] coords Coordinates of the tetrahedron
//! \param[in] seed Random number generation seed
//! \return Sampled position within the tetrahedron
Position sample_tet(std::array<Position, 4> coords, uint64_t* seed) const;
template<typename V>
Position sample_tet(span<V> coords, uint64_t* seed) const
{
// Uniform distribution
double s = prn(seed);
double t = prn(seed);
double u = prn(seed);
// From PyNE implementation of moab tet sampling C. Rocchini & P. Cignoni
// (2000) Generating Random Points in a Tetrahedron, Journal of Graphics
// Tools, 5:4, 9-12, DOI: 10.1080/10867651.2000.10487528
if (s + t > 1) {
s = 1.0 - s;
t = 1.0 - t;
}
if (s + t + u > 1) {
if (t + u > 1) {
double old_t = t;
t = 1.0 - u;
u = 1.0 - s - old_t;
} else if (t + u <= 1) {
double old_s = s;
s = 1.0 - t - u;
u = old_s + t + u - 1;
}
}
V result = s * (coords[1] - coords[0]) + t * (coords[2] - coords[0]) +
u * (coords[3] - coords[0]) + coords[0];
return {result[0], result[1], result[2]};
}
// Data members
double length_multiplier_ {

125
include/openmc/xdg.h Normal file
View file

@ -0,0 +1,125 @@
#ifndef OPENMC_XDG_H
#define OPENMC_XDG_H
namespace openmc {
extern "C" const bool XDG_ENABLED;
}
#ifdef OPENMC_XDG_ENABLED
#include "xdg/xdg.h"
#include "openmc/mesh.h"
#include "openmc/position.h"
#include "openmc/xml_interface.h"
namespace openmc {
class XDGMesh : public UnstructuredMesh {
public:
//----------------------------------------------------------------------------
// Constructors
XDGMesh() = default;
XDGMesh(pugi::xml_node node);
XDGMesh(hid_t group);
XDGMesh(const std::string& filename, double length_multiplier = 1.0);
XDGMesh(std::shared_ptr<xdg::XDG> external_xdg);
static const std::string mesh_type;
//----------------------------------------------------------------------------
// Methods
//! Get the underlying XDG instance
//!
//! \return Shared pointer to the XDG instance
const std::shared_ptr<xdg::XDG>& xdg_instance() const { return xdg_; }
//! Check whether a bin index is valid
//!
//! \param[in] bin Bin index to check
//! \return True if the bin index is in [0, n_bins())
bool bin_is_valid(int bin) const { return bin >= 0 && bin < n_bins(); }
std::string get_mesh_type() const override { return mesh_type; }
//! Convert a mesh bin index to an XDG MeshID
//!
//! \param[in] bin Bin index to convert
//! \return XDG MeshID corresponding to the bin
xdg::MeshID bin_to_mesh_id(int bin) const;
//! Convert an XDG MeshID to a mesh bin index
//!
//! \param[in] id XDG MeshID to convert
//! \return Bin index corresponding to the MeshID, or -1 if invalid
int mesh_id_to_bin(xdg::MeshID id) const;
//! Get the name of the underlying mesh library
//!
//! \return Name of the mesh library being used in XDG
std::string library() const override;
//----------------------------------------------------------------------------
// Overridden Methods
//! Perform any preparation needed to support use in mesh filters
void prepare_for_point_location() override;
Position sample_element(int32_t bin, uint64_t* seed) const override;
void bins_crossed(Position r0, Position r1, const Direction& u,
vector<int>& bins, vector<double>& lengths) const override;
int get_bin(Position r) const override;
int n_bins() const override;
int n_surface_bins() const override;
std::pair<vector<double>, vector<double>> plot(
Position plot_ll, Position plot_ur) const override;
//! Add a score to the mesh instance
void add_score(const std::string& score) override {};
//! Remove all scores from the mesh instance
void remove_scores() override {};
//! Set data for a score
void set_score_data(const std::string& score, const vector<double>& values,
const vector<double>& std_dev) override {};
//! Write the mesh with any current tally data
void write(const std::string& base_filename) const override;
Position centroid(int bin) const override;
int n_vertices() const override;
Position vertex(int id) const override;
std::vector<int> connectivity(int id) const override;
//! Get the volume of a mesh bin
//
//! \param[in] bin Bin to return the volume for
//! \return Volume of the bin
double volume(int bin) const override;
private:
void initialize() override;
//----------------------------------------------------------------------------
// Private data members
std::shared_ptr<xdg::XDG> xdg_; //!< XDG instance
xdg::MeshLibrary mesh_library_ {
xdg::MeshLibrary::LIBMESH}; //!< Mesh library type
};
} // namespace openmc
#endif // OPENMC_XDG_ENABLED
#endif // OPENMC_XDG_H

1
openmc/__init__.py
View file

@ -34,6 +34,7 @@ from openmc.plotter import *
from openmc.search import *
from openmc.polynomial import *
from openmc.tracks import *
from openmc.xdg import *
from .config import *
# Import a few names from the model module

4
openmc/filter.py
View file

@ -920,11 +920,13 @@ class MeshFilter(Filter):
def mesh(self, mesh):
cv.check_type('filter mesh', mesh, openmc.MeshBase)
self._mesh = mesh
if isinstance(mesh, openmc.UnstructuredMesh):
if isinstance(mesh, (openmc.UnstructuredMesh, openmc.XDGMesh)):
if mesh.has_statepoint_data:
self.bins = list(range(len(mesh.volumes)))
else:
self.bins = []
elif isinstance(mesh, openmc.XDGMesh):
self.bins = []
else:
self.bins = list(mesh.indices)

3
openmc/lib/__init__.py
View file

@ -40,6 +40,9 @@ else:
def _dagmc_enabled():
return c_bool.in_dll(_dll, "DAGMC_ENABLED").value
def _xdg_enabled():
return c_bool.in_dll(_dll, "XDG_ENABLED").value
def _coord_levels():
return c_int.in_dll(_dll, "n_coord_levels").value

25
openmc/mesh.py
View file

@ -301,6 +301,8 @@ class MeshBase(IDManagerMixin, ABC):
return SphericalMesh.from_hdf5(group, mesh_id, mesh_name)
elif mesh_type == 'unstructured':
return UnstructuredMesh.from_hdf5(group, mesh_id, mesh_name)
elif mesh_type == 'xdg':
return openmc.XDGMesh.from_hdf5(group, mesh_id, mesh_name)
else:
raise ValueError('Unrecognized mesh type: "' + mesh_type + '"')
@ -346,6 +348,8 @@ class MeshBase(IDManagerMixin, ABC):
mesh = CylindricalMesh.from_xml_element(elem)
elif mesh_type == 'spherical':
mesh = SphericalMesh.from_xml_element(elem)
elif mesh_type == 'xdg':
mesh = openmc.XDGMesh.from_xml_element(elem)
elif mesh_type == 'unstructured':
mesh = UnstructuredMesh.from_xml_element(elem)
else:
@ -3262,18 +3266,17 @@ class UnstructuredMesh(MeshBase):
def from_hdf5(cls, group: h5py.Group, mesh_id: int, name: str):
filename = group["filename"][()].decode()
library = group["library"][()].decode()
if "options" in group.attrs:
options = group.attrs['options'].decode()
else:
options = None
mesh = cls(
filename=filename,
library=library,
mesh_id=mesh_id,
name=name,
options=options,
)
kwargs = {'filename': filename,
'library': library,
'mesh_id': mesh_id,
'name': name}
if "options" in group.attrs:
kwargs['options'] = group.attrs['options'].decode()
mesh = cls(**kwargs)
mesh._has_statepoint_data = True
vol_data = group["volumes"][()]
mesh.volumes = np.reshape(vol_data, (vol_data.shape[0],))

107
openmc/xdg.py Normal file
View file

@ -0,0 +1,107 @@
from collections.abc import Iterable
from numbers import Integral
from functools import wraps
import h5py
import lxml.etree as ET
import openmc
import openmc.checkvalue as cv
from ._xml import get_text
from .bounding_box import BoundingBox
from .checkvalue import PathLike
from .utility_funcs import input_path
class XDGMesh(openmc.UnstructuredMesh):
"""A 3D unstructured mesh supported by the XDG library. Various mesh
backends are supported in XDG, including MOAB and libMesh. For more
information on supported mesh types and libraries, see
https://xdg-org.github.io/xdg/.
This class is meant to serve as a reference to an unstructured mesh to be
applied in an OpenMC model in one of the following ways:
1. As a volumetric mesh for an tally MeshFilter (see
:class:`openmc.MeshFilter`)
2. As a surface mesh for an XDGUniverse (see :class:`openmc.XDGUniverse`)
3. As a volumetric mesh for an XDGUniverse (see :class:`openmc.XDGUniverse`)
Parameters
----------
filename : path-like
Location of the unstructured mesh file. Supported files for 'moab'
library are .h5, .vtk and .e (exodus) depending on the MOAB build
configuration. Supported files for 'libmesh' library are exodus mesh
files .exo.
library : {'moab', 'libmesh'}
Mesh library used for the unstructured mesh tally
mesh_id : int
Unique identifier for the mesh
name : str
Name of the mesh
Attributes
----------
id : int
Unique identifier for the mesh
name : str
Name of the mesh
filename : str
Name of the file containing the unstructured mesh
library : {'moab', 'libmesh'}
Mesh library used for the unstructured mesh tally
"""
def __init__(self, filename: PathLike, library: str | None = None, mesh_id: int | None = None,
name: str = ''):
super().__init__(mesh_id=mesh_id,
name=name,
filename=filename,
library=library)
# set library based on file extension if not provided by the user
if library is None:
if filename.suffix in ('.h5m', '.vtk', '.e'):
library = 'moab'
elif filename.suffix in ('.exo',):
library = 'libmesh'
if library is None:
raise ValueError(f"Unable to determine mesh library from file extension {filename.suffix}. "
"Please specify the mesh library type explicitly.")
self.library = library
def to_xml_element(self):
"""Return XML representation of the mesh
Returns
-------
element : lxml.etree._Element
XML element containing mesh data
"""
element = super().to_xml_element()
element.set("type", "xdg")
element.set("library", self._library)
return element
@classmethod
def from_xml_element(cls, elem: ET.Element):
"""Generate unstructured mesh object from XML element
Parameters
----------
elem : lxml.etree._Element
XML element
Returns
-------
openmc.UnstructuredMesh
UnstructuredMesh generated from an XML element
"""
mesh_id = int(get_text(elem, 'id'))
filename = get_text(elem, 'filename')
library = get_text(elem, 'library')
return cls(filename, library, mesh_id)

12
src/initialize.cpp
View file

@ -42,6 +42,10 @@
#include "libmesh/libmesh.h"
#endif
#ifdef OPENMC_XDG_ENABLED
#include "xdg/config.h"
#endif
int openmc_init(int argc, char* argv[], const void* intracomm)
{
using namespace openmc;
@ -85,6 +89,14 @@ int openmc_init(int argc, char* argv[], const void* intracomm)
settings::libmesh_comm = &(settings::libmesh_init->comm());
}
#if defined(OPENMC_XDG_ENABLED) && defined(XDG_ENABLE_LIBMESH)
// Set the external libMesh initialization and communicator for XDG if
// libMesh was initialized externally. If libMesh was initialized internally,
// the XDG config will use the internal initialization and communicator.
xdg::config::external_libmesh_init = settings::libmesh_init.get();
xdg::config::external_libmesh_comm = settings::libmesh_comm;
#endif
#endif
// Start total and initialization timer

59
src/mesh.cpp
View file

@ -56,6 +56,8 @@
#include "moab/FileOptions.hpp"
#endif
#include "openmc/xdg.h"
namespace openmc {
//==============================================================================
@ -348,6 +350,10 @@ const std::unique_ptr<Mesh>& Mesh::create(
mesh_library == MOABMesh::mesh_lib_type) {
model::meshes.push_back(make_unique<MOABMesh>(dataset));
#endif
#ifdef OPENMC_XDG_ENABLED
} else if (mesh_type == XDGMesh::mesh_type) {
model::meshes.push_back(make_unique<XDGMesh>(dataset));
#endif
#ifdef OPENMC_LIBMESH_ENABLED
} else if (mesh_type == UnstructuredMesh::mesh_type &&
mesh_library == LibMesh::mesh_lib_type) {
@ -799,12 +805,12 @@ UnstructuredMesh::UnstructuredMesh(pugi::xml_node node) : Mesh(node)
n_dimension_ = 3;
// check the mesh type
if (check_for_node(node, "type")) {
auto temp = get_node_value(node, "type", true, true);
if (temp != mesh_type) {
fatal_error(fmt::format("Invalid mesh type: {}", temp));
}
}
// if (check_for_node(node, "type")) {
// auto temp = get_node_value(node, "type", true, true);
// if (temp != mesh_type) {
// fatal_error(fmt::format("Invalid mesh type: {}", temp));
// }
// }
// check if a length unit multiplier was specified
if (check_for_node(node, "length_multiplier")) {
@ -895,36 +901,6 @@ void UnstructuredMesh::determine_bounds()
upper_right_ = {xmax, ymax, zmax};
}
Position UnstructuredMesh::sample_tet(
std::array<Position, 4> coords, uint64_t* seed) const
{
// Uniform distribution
double s = prn(seed);
double t = prn(seed);
double u = prn(seed);
// From PyNE implementation of moab tet sampling C. Rocchini & P. Cignoni
// (2000) Generating Random Points in a Tetrahedron, Journal of Graphics
// Tools, 5:4, 9-12, DOI: 10.1080/10867651.2000.10487528
if (s + t > 1) {
s = 1.0 - s;
t = 1.0 - t;
}
if (s + t + u > 1) {
if (t + u > 1) {
double old_t = t;
t = 1.0 - u;
u = 1.0 - s - old_t;
} else if (t + u <= 1) {
double old_s = s;
s = 1.0 - t - u;
u = old_s + t + u - 1;
}
}
return s * (coords[1] - coords[0]) + t * (coords[2] - coords[0]) +
u * (coords[3] - coords[0]) + coords[0];
}
const std::string UnstructuredMesh::mesh_type = "unstructured";
std::string UnstructuredMesh::get_mesh_type() const
@ -992,7 +968,6 @@ void UnstructuredMesh::to_hdf5_inner(hid_t mesh_group) const
connectivity.slice(i) = -1;
}
}
// warn users that some elements were skipped
if (num_elem_skipped > 0) {
warning(fmt::format("The connectivity of {} elements "
@ -3173,7 +3148,6 @@ std::string MOABMesh::library() const
// Sample position within a tet for MOAB type tets
Position MOABMesh::sample_element(int32_t bin, uint64_t* seed) const
{
moab::EntityHandle tet_ent = get_ent_handle_from_bin(bin);
// Get vertex coordinates for MOAB tet
@ -3191,12 +3165,8 @@ Position MOABMesh::sample_element(int32_t bin, uint64_t* seed) const
fatal_error("Failed to get tet coords");
}
std::array<Position, 4> tet_verts;
for (int i = 0; i < 4; i++) {
tet_verts[i] = {p[i][0], p[i][1], p[i][2]};
}
// Samples position within tet using Barycentric stuff
return this->sample_tet(tet_verts, seed);
return this->sample_tet<moab::CartVect>({p, 4}, seed);
}
double MOABMesh::tet_volume(moab::EntityHandle tet) const
@ -3688,7 +3658,8 @@ Position LibMesh::sample_element(int32_t bin, uint64_t* seed) const
tet_verts[i] = {node_ref(0), node_ref(1), node_ref(2)};
}
// Samples position within tet using Barycentric coordinates
Position sampled_position = this->sample_tet(tet_verts, seed);
Position sampled_position =
this->sample_tet<Position>({tet_verts.begin(), tet_verts.end()}, seed);
if (length_multiplier_ > 0.0) {
return length_multiplier_ * sampled_position;
} else {

5
src/output.cpp
View file

@ -317,6 +317,7 @@ void print_build_info()
std::string mpi(n);
std::string phdf5(n);
std::string dagmc(n);
std::string xdg(n);
std::string libmesh(n);
std::string png(n);
std::string profiling(n);
@ -333,6 +334,9 @@ void print_build_info()
#ifdef OPENMC_DAGMC_ENABLED
dagmc = y;
#endif
#ifdef OPENMC_XDG_ENABLED
xdg = y;
#endif
#ifdef OPENMC_LIBMESH_ENABLED
libmesh = y;
#endif
@ -364,6 +368,7 @@ void print_build_info()
fmt::print("Parallel HDF5 enabled: {}\n", phdf5);
fmt::print("PNG support: {}\n", png);
fmt::print("DAGMC support: {}\n", dagmc);
fmt::print("XDG support: {}\n", xdg);
fmt::print("libMesh support: {}\n", libmesh);
fmt::print("Coverage testing: {}\n", coverage);
fmt::print("Profiling flags: {}\n", profiling);

259
src/xdg.cpp Normal file
View file

@ -0,0 +1,259 @@
#include "openmc/xdg.h"
#include <algorithm> // for remove_if
#include <memory> // for shared_ptr
#include <string> // for string
#include <utility> // for pair
#include <vector> // for vector
#include <fmt/core.h>
#ifdef OPENMC_XDG_ENABLED
#include "xdg/xdg.h"
#endif
#include "openmc/constants.h"
#include "openmc/container_util.h"
#include "openmc/error.h"
#include "openmc/file_utils.h"
#include "openmc/geometry.h"
#include "openmc/geometry_aux.h"
#include "openmc/hdf5_interface.h"
#include "openmc/material.h"
#include "openmc/settings.h"
#include "openmc/string_utils.h"
namespace openmc {
#ifdef OPENMC_XDG_ENABLED
const bool XDG_ENABLED = true;
#else
const bool XDG_ENABLED = false;
#endif
} // namespace openmc
#ifdef OPENMC_XDG_ENABLED
namespace openmc {
//==============================================================================
// XDG Mesh implementation
//==============================================================================
const std::string XDGMesh::mesh_type = "xdg";
XDGMesh::XDGMesh(pugi::xml_node node) : UnstructuredMesh(node)
{
std::string mesh_lib = get_node_value(node, "library", true, true);
if (mesh_lib == "moab") {
mesh_library_ = xdg::MeshLibrary::MOAB;
} else if (mesh_lib == "libmesh") {
mesh_library_ = xdg::MeshLibrary::LIBMESH;
} else {
fatal_error(fmt::format("Invalid mesh library specified in XML: {}. "
"Valid options are 'moab' and 'libmesh'.",
mesh_lib));
}
initialize();
}
XDGMesh::XDGMesh(hid_t group) : UnstructuredMesh(group)
{
std::string mesh_lib;
read_dataset(group, "library", mesh_lib);
if (mesh_lib == "moab") {
mesh_library_ = xdg::MeshLibrary::MOAB;
} else if (mesh_lib == "libmesh") {
mesh_library_ = xdg::MeshLibrary::LIBMESH;
} else {
fatal_error(fmt::format("Invalid mesh library specified in HDF5: {}. "
"Valid options are 'moab' and 'libmesh'.",
mesh_lib));
}
initialize();
}
XDGMesh::XDGMesh(const std::string& filename, double length_multiplier)
{
filename_ = filename;
set_length_multiplier(length_multiplier);
initialize();
}
XDGMesh::XDGMesh(std::shared_ptr<xdg::XDG> external_xdg)
{
xdg_ = external_xdg;
filename_ = "unknown (external file)";
initialize();
}
void XDGMesh::initialize()
{
if (xdg_)
return;
// create XDGMesh instance
xdg_ = xdg::XDG::create(mesh_library_);
// load XDGMesh file
if (!file_exists(filename_)) {
fatal_error(fmt::format("Mesh file \"{}\" does not exist", filename_));
}
xdg_->mesh_manager()->load_file(filename_);
xdg_->mesh_manager()->init();
xdg_->mesh_manager()->parse_metadata();
auto global_bbox = xdg_->mesh_manager()->global_bounding_box();
Position lower_left =
length_multiplier_ *
Position(global_bbox.min_x, global_bbox.min_y, global_bbox.min_z);
Position upper_right =
length_multiplier_ *
Position(global_bbox.max_x, global_bbox.max_y, global_bbox.max_z);
lower_left_ = {lower_left.x, lower_left.y, lower_left.z};
upper_right_ = {upper_right.x, upper_right.y, upper_right.z};
}
void XDGMesh::prepare_for_point_location()
{
xdg_->prepare_raytracer();
}
Position XDGMesh::sample_element(int32_t bin, uint64_t* seed) const
{
auto vertices = xdg_->mesh_manager()->element_vertices(bin_to_mesh_id(bin));
Position sampled_position = this->sample_tet<xdg::Vertex>(vertices, seed);
if (length_multiplier_ > 0.0) {
sampled_position *= length_multiplier_;
}
return sampled_position;
}
void XDGMesh::bins_crossed(Position r0, Position r1, const Direction& u,
vector<int>& bins, vector<double>& lengths) const
{
xdg::Position p0 {r0.x, r0.y, r0.z};
xdg::Position p1 {r1.x, r1.y, r1.z};
double inv_length = 1 / (p1 - p0).length();
auto track_segments = xdg_->segments(p0, p1);
// remove elements with lengths of zero
track_segments.erase(
std::remove_if(track_segments.begin(), track_segments.end(),
[](const std::pair<xdg::MeshID, double>& p) { return p.second == 0.0; }),
track_segments.end());
for (const auto& track_segment : track_segments) {
bins.push_back(mesh_id_to_bin(track_segment.first));
lengths.push_back(track_segment.second * inv_length);
}
}
int XDGMesh::get_bin(Position r) const
{
xdg::Position p {r.x, r.y, r.z};
if (length_multiplier_ > 0.0) {
p /= length_multiplier_;
}
return mesh_id_to_bin(xdg_->find_element(p));
}
int XDGMesh::n_bins() const
{
return xdg_->mesh_manager()->num_volume_elements();
}
int XDGMesh::n_surface_bins() const
{
return 4 * n_bins();
}
std::pair<vector<double>, vector<double>> XDGMesh::plot(
Position plot_ll, Position plot_ur) const
{
fatal_error("Plot of XDGMesh mesh not implemented");
return {};
}
std::string XDGMesh::library() const
{
if (mesh_library_ == xdg::MeshLibrary::LIBMESH) {
return "libmesh";
} else if (mesh_library_ == xdg::MeshLibrary::MOAB) {
return "moab";
}
}
void XDGMesh::write(const std::string& base_filename) const
{
warning("XDGMesh mesh write from C++ not implemented");
}
Position XDGMesh::centroid(int bin) const
{
auto element_vertices =
xdg_->mesh_manager()->element_vertices(bin_to_mesh_id(bin));
xdg::Vertex center {0.0, 0.0, 0.0};
for (const auto& v : element_vertices) {
center += v;
}
center /= double(element_vertices.size());
if (length_multiplier_ > 0.0) {
center *= length_multiplier_;
}
return {center[0], center[1], center[2]};
}
int XDGMesh::n_vertices() const
{
return xdg_->mesh_manager()->num_vertices();
}
Position XDGMesh::vertex(int id) const
{
xdg::MeshID mesh_id = xdg_->mesh_manager()->vertex_id(id);
auto v = xdg_->mesh_manager()->vertex_coordinates(mesh_id);
if (length_multiplier_ > 0.0) {
v *= length_multiplier_;
}
return {v[0], v[1], v[2]};
}
std::vector<int> XDGMesh::connectivity(int id) const
{
auto conn = xdg_->mesh_manager()->element_connectivity(bin_to_mesh_id(id));
for (auto& c : conn) {
c = xdg_->mesh_manager()->vertex_index(c);
}
return conn;
}
double XDGMesh::volume(int bin) const
{
double vol = xdg_->mesh_manager()->element_volume(bin_to_mesh_id(bin));
if (length_multiplier_ > 0.0) {
vol *= length_multiplier_ * length_multiplier_ * length_multiplier_;
}
return vol;
}
xdg::MeshID XDGMesh::bin_to_mesh_id(int bin) const
{
return xdg_->mesh_manager()->element_id(bin);
}
int32_t XDGMesh::mesh_id_to_bin(xdg::MeshID id) const
{
if (id < 0)
return -1;
return xdg_->mesh_manager()->element_index(id);
}
} // namespace openmc
#endif // XDG

2
tests/regression_tests/unstructured_mesh/inputs_true.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true0.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true1.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true10.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true11.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true12.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true13.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true14.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true15.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true2.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true3.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true8.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

2
tests/regression_tests/unstructured_mesh/inputs_true9.dat
View file

@ -48,7 +48,7 @@
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 0.0"/>
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>

4
tests/regression_tests/unstructured_mesh/test.py
View file

@ -225,11 +225,11 @@ def model():
settings.batches = 10
# source setup
r = openmc.stats.Uniform(a=0.0, b=0.0)
r = openmc.stats.Uniform(a=0.0, b=9.0)
cos_theta = openmc.stats.Discrete(x=[1.0], p=[1.0])
phi = openmc.stats.Discrete(x=[0.0], p=[1.0])
space = openmc.stats.SphericalIndependent(r, cos_theta, phi)
space = openmc.stats.SphericalIndependent(r=r, cos_theta=cos_theta, phi=phi)
energy = openmc.stats.Discrete(x=[15.e+06], p=[1.0])
source = openmc.IndependentSource(space=space, energy=energy)
settings.source = source

0
tests/regression_tests/xdg/__init__.py Normal file
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0
tests/regression_tests/xdg/tallies/__init__.py Normal file
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90
tests/regression_tests/xdg/tallies/inputs_true0_libmesh.dat Normal file
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@ -0,0 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

90
tests/regression_tests/xdg/tallies/inputs_true0_moab.dat Normal file
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@ -0,0 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="moab">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

90
tests/regression_tests/xdg/tallies/inputs_true1_libmesh.dat Normal file
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@ -0,0 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets.exo</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

90
tests/regression_tests/xdg/tallies/inputs_true2_libmesh.dat Normal file
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@ -0,0 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="moab">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="10.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-10.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="10.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets_w_holes.exo</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="15.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="15.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="moab">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="15.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets.exo</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="15.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="15.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="moab">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

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tests/regression_tests/xdg/tallies/inputs_true7_libmesh.dat Normal file
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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" name="fuel" depletable="true">
<density value="4.5" units="g/cc"/>
<nuclide name="U235" ao="1.0"/>
</material>
<material id="2" name="zircaloy">
<density value="5.77" units="g/cc"/>
<nuclide name="Zr90" ao="0.5145"/>
<nuclide name="Zr91" ao="0.1122"/>
<nuclide name="Zr92" ao="0.1715"/>
<nuclide name="Zr94" ao="0.1738"/>
<nuclide name="Zr96" ao="0.028"/>
</material>
<material id="3" name="water">
<density value="0.07416" units="atom/b-cm"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="fuel" material="1" region="-2 1 -4 3 -6 5" universe="1"/>
<cell id="2" name="clad" material="2" region="(2 | -1 | 4 | -3 | 6 | -5) (-8 7 -10 9 -12 11)" universe="1"/>
<cell id="3" name="water" material="3" region="(8 | -7 | 10 | -9 | 12 | -11) (-14 13 -16 15 -18 17)" universe="1"/>
<surface id="1" type="x-plane" coeffs="-5.0"/>
<surface id="2" type="x-plane" coeffs="5.0"/>
<surface id="3" type="y-plane" coeffs="-5.0"/>
<surface id="4" type="y-plane" coeffs="5.0"/>
<surface id="5" type="z-plane" coeffs="-5.0"/>
<surface id="6" type="z-plane" coeffs="5.0"/>
<surface id="7" type="x-plane" coeffs="-6.0"/>
<surface id="8" type="x-plane" coeffs="6.0"/>
<surface id="9" type="y-plane" coeffs="-6.0"/>
<surface id="10" type="y-plane" coeffs="6.0"/>
<surface id="11" type="z-plane" coeffs="-6.0"/>
<surface id="12" type="z-plane" coeffs="6.0"/>
<surface id="13" type="x-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="14" type="x-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="15" type="y-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="16" type="y-plane" boundary="vacuum" coeffs="15.0"/>
<surface id="17" type="z-plane" boundary="vacuum" coeffs="-15.0"/>
<surface id="18" type="z-plane" boundary="vacuum" coeffs="15.0"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source type="independent" strength="1.0" particle="neutron">
<space type="spherical" origin="0.0 0.0 0.0">
<r type="uniform" parameters="0.0 9.0"/>
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" type="xdg" library="libmesh">
<filename>test_mesh_tets_w_holes.exo</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="xdg mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

311
tests/regression_tests/xdg/tallies/test.py Normal file
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import glob
from pathlib import Path
import numpy as np
import pytest
import openmc
import openmc.lib
from openmc.xdg import XDGMesh
from tests.testing_harness import PyAPITestHarness
class XDGMeshTallyTest(PyAPITestHarness):
ELEM_PER_VOXEL = 12
def __init__(
self,
statepoint_name,
model,
inputs_true,
mesh_filename,
mesh_kind,
holes=None,
scale_factor=10.0,
):
super().__init__(statepoint_name, model, inputs_true)
print(f"Running test with mesh file: {mesh_filename} and inputs file: {inputs_true}")
self.mesh_filename = mesh_filename
self.mesh_kind = mesh_kind
self.holes = holes
self.scale_bounding_cell(scale_factor)
def scale_bounding_cell(self, scale_factor):
geometry = self._model.geometry
for surface in geometry.get_all_surfaces().values():
if surface.boundary_type != 'vacuum':
continue
for coeff in surface._coefficients:
surface._coefficients[coeff] *= scale_factor
def _compare_results(self):
with openmc.StatePoint(self._sp_name) as sp:
xdg_mesh = None
for mesh in sp.meshes.values():
if isinstance(mesh, XDGMesh):
xdg_mesh = mesh
break
assert xdg_mesh is not None
assert Path(xdg_mesh.filename).name == Path(self.mesh_filename).name
if self.mesh_kind == "tet":
exp_vertex = (-10.0, -10.0, -10.0)
exp_centroid = (-8.75, -9.75, -9.25)
else:
exp_vertex = (-10.0, -10.0, 10.0)
exp_centroid = (-9.0, -9.0, 9.0)
np.testing.assert_array_equal(xdg_mesh.vertices[0], exp_vertex)
np.testing.assert_array_equal(xdg_mesh.centroid(0), exp_centroid)
reg_mesh_data = None
xdg_mesh_data = None
xdg_tally = None
for tally in sp.tallies.values():
if tally.contains_filter(openmc.MeshFilter):
flt = tally.find_filter(openmc.MeshFilter)
if isinstance(flt.mesh, openmc.RegularMesh):
reg_mesh_data = self.get_mesh_tally_data(tally)
else:
xdg_tally = tally
xdg_mesh_data = self.get_mesh_tally_data(tally, structured=True)
assert reg_mesh_data is not None
assert xdg_mesh_data is not None
if self.holes:
reg_mesh_data = np.delete(reg_mesh_data, self.holes)
decimals = 10 if xdg_tally.estimator == 'collision' else 8
np.testing.assert_array_almost_equal(
np.sort(xdg_mesh_data),
np.sort(reg_mesh_data),
decimals
)
def get_mesh_tally_data(self, tally, structured=False):
data = tally.get_reshaped_data(value='mean')
if structured:
data = data.reshape((-1, self.ELEM_PER_VOXEL))
else:
data.shape = (data.size, 1)
return np.sum(data, axis=1)
def update_results(self):
"""Update inputs_true.dat without storing results_true.dat."""
try:
self._build_inputs()
inputs = self._get_inputs()
self._write_inputs(inputs)
self._overwrite_inputs()
self._run_openmc()
self._test_output_created()
finally:
self._cleanup()
def _cleanup(self):
super()._cleanup()
output = glob.glob('tally*.vtk')
output += glob.glob('tally*.e')
for f in output:
Path(f).unlink(missing_ok=True)
@pytest.fixture
def model():
openmc.reset_auto_ids()
model = openmc.Model()
### Materials ###
materials = openmc.Materials()
fuel_mat = openmc.Material(name="fuel")
fuel_mat.add_nuclide("U235", 1.0)
fuel_mat.set_density('g/cc', 4.5)
materials.append(fuel_mat)
zirc_mat = openmc.Material(name="zircaloy")
zirc_mat.add_element("Zr", 1.0)
zirc_mat.set_density("g/cc", 5.77)
materials.append(zirc_mat)
water_mat = openmc.Material(name="water")
water_mat.add_nuclide("H1", 2.0)
water_mat.add_nuclide("O16", 1.0)
water_mat.set_density("atom/b-cm", 0.07416)
materials.append(water_mat)
model.materials = materials
### Geometry ###
fuel_boundary = openmc.model.RectangularParallelepiped(*[-5.0, 5.0]*3)
clad_boundary = openmc.model.RectangularParallelepiped(*[-6.0, 6.0]*3)
fuel_cell = openmc.Cell(name="fuel")
fuel_cell.region = -fuel_boundary
fuel_cell.fill = fuel_mat
clad_cell = openmc.Cell(name="clad")
clad_cell.region = +fuel_boundary & -clad_boundary
clad_cell.fill = zirc_mat
# set bounding cell dimension to one
# this will be updated later according to the test case parameters
boundary = openmc.model.RectangularParallelepiped(*[-1.0, 1.0]*3,
boundary_type='vacuum')
water_cell = openmc.Cell(name="water")
water_cell.region = +clad_boundary & -boundary
water_cell.fill = water_mat
# create a containing universe
model.geometry = openmc.Geometry([fuel_cell, clad_cell, water_cell])
### Reference Tally ###
# create meshes and mesh filters
regular_mesh = openmc.RegularMesh()
regular_mesh.dimension = (10, 10, 10)
regular_mesh.lower_left = (-10.0, -10.0, -10.0)
regular_mesh.upper_right = (10.0, 10.0, 10.0)
regular_mesh_filter = openmc.MeshFilter(mesh=regular_mesh)
regular_mesh_tally = openmc.Tally(name="regular mesh tally")
regular_mesh_tally.filters = [regular_mesh_filter]
regular_mesh_tally.scores = ['flux']
model.tallies = openmc.Tallies([regular_mesh_tally])
### Settings ###
model.settings.run_mode = 'fixed source'
model.settings.particles = 1000
model.settings.batches = 10
# source setup
r = openmc.stats.Uniform(a=0.0, b=9.0)
cos_theta = openmc.stats.delta_function(1.0)
phi = openmc.stats.delta_function(0.0)
space = openmc.stats.SphericalIndependent(r, cos_theta, phi)
energy = openmc.stats.delta_function(15e6)
source = openmc.IndependentSource(space=space, energy=energy)
model.settings.source = source
return model
MESH_CASES = (
{
"mesh_filename": "test_mesh_tets.e",
"mesh_kind": "tet",
"holes": None,
"elem_per_voxel": 12,
"external_geom": False,
"libraries": ("moab", "libmesh"),
},
{
"mesh_filename": "test_mesh_tets.exo",
"mesh_kind": "tet",
"holes": None,
"elem_per_voxel": 12,
"external_geom": False,
"libraries": ("libmesh",),
},
{
"mesh_filename": "test_mesh_tets_w_holes.e",
"mesh_kind": "tet",
"holes": (333, 90, 77),
"elem_per_voxel": 12,
"external_geom": False,
"libraries": ("moab", "libmesh"),
},
{
"mesh_filename": "test_mesh_tets_w_holes.exo",
"mesh_kind": "tet",
"holes": (333, 90, 77),
"elem_per_voxel": 12,
"external_geom": False,
"libraries": ("libmesh",),
},
{
"mesh_filename": "test_mesh_tets.e",
"mesh_kind": "tet",
"holes": None,
"elem_per_voxel": 12,
"external_geom": True,
"libraries": ("moab", "libmesh"),
},
{
"mesh_filename": "test_mesh_tets.exo",
"mesh_kind": "tet",
"holes": None,
"elem_per_voxel": 12,
"external_geom": True,
"libraries": ("libmesh",),
},
{
"mesh_filename": "test_mesh_tets_w_holes.e",
"mesh_kind": "tet",
"holes": (333, 90, 77),
"elem_per_voxel": 12,
"external_geom": True,
"libraries": ("moab", "libmesh"),
},
{
"mesh_filename": "test_mesh_tets_w_holes.exo",
"mesh_kind": "tet",
"holes": (333, 90, 77),
"elem_per_voxel": 12,
"external_geom": True,
"libraries": ("libmesh",),
}
)
test_cases = []
test_case_ids = []
for i, mesh_case in enumerate(MESH_CASES):
for library in mesh_case["libraries"]:
test_cases.append({
"inputs_true": f"inputs_true{i}_{library}.dat",
"library": library,
**{k: v for k, v in mesh_case.items() if k != "libraries"},
})
mesh_stem = Path(mesh_case["mesh_filename"]).stem
geom_mode = "external-geom" if mesh_case["external_geom"] else "bounded-geom"
holes = "holes" if mesh_case["holes"] else "solid"
test_case_ids.append(f"{library}-{mesh_stem}-{holes}-{geom_mode}")
@pytest.mark.parametrize("test_opts", test_cases, ids=test_case_ids)
def test_xdg_mesh_tallies(model, test_opts):
if not openmc.lib._xdg_enabled():
pytest.skip("XDG is not enabled in this build.")
# reference mesh tally
regular_mesh_tally = model.tallies[0]
regular_mesh_tally.estimator = 'collision'
# add analogous XDG mesh tally
xdg_mesh = XDGMesh(test_opts["mesh_filename"], test_opts["library"])
xdg_filter = openmc.MeshFilter(mesh=xdg_mesh)
xdg_tally = openmc.Tally(name="xdg mesh tally")
xdg_tally.filters = [xdg_filter]
xdg_tally.scores = ['flux']
xdg_tally.estimator = 'collision'
model.tallies.append(xdg_tally)
harness = XDGMeshTallyTest(
'statepoint.10.h5',
model,
test_opts["inputs_true"],
test_opts["mesh_filename"],
test_opts["mesh_kind"],
test_opts["holes"],
scale_factor=15.0 if test_opts["external_geom"] else 10.0,
)
harness.ELEM_PER_VOXEL = test_opts["elem_per_voxel"]
harness.main()

1
tests/regression_tests/xdg/tallies/test_mesh_hexes.e Symbolic link
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../../unstructured_mesh/test_mesh_hexes.e

1
tests/regression_tests/xdg/tallies/test_mesh_hexes.exo Symbolic link
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../../unstructured_mesh/test_mesh_hexes.exo

1
tests/regression_tests/xdg/tallies/test_mesh_tets.e Symbolic link
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../../unstructured_mesh/test_mesh_tets.e

1
tests/regression_tests/xdg/tallies/test_mesh_tets.exo Symbolic link
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../../unstructured_mesh/test_mesh_tets.exo

1
tests/regression_tests/xdg/tallies/test_mesh_tets_w_holes.e Symbolic link
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../../unstructured_mesh/test_mesh_tets_w_holes.e

1
tests/regression_tests/xdg/tallies/test_mesh_tets_w_holes.exo Symbolic link
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../../unstructured_mesh/test_mesh_tets_w_holes.exo

29
tools/ci/gha-build-moab.sh Executable file
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#!/bin/bash
set -ex
MOAB_BRANCH='5.5.1'
MOAB_REPO='https://bitbucket.org/fathomteam/moab/'
MOAB_INSTALL_DIR=$HOME/MOAB/
pushd $HOME
if [[ -d $MOAB_INSTALL_DIR/lib ]]; then
popd
exit 0
fi
mkdir -p MOAB
cd MOAB
git clone -b $MOAB_BRANCH $MOAB_REPO moab
mkdir build
cd build
cmake ../moab \
-DENABLE_HDF5=ON \
-DENABLE_NETCDF=ON \
-DBUILD_SHARED_LIBS=ON \
-DCMAKE_INSTALL_PREFIX=$MOAB_INSTALL_DIR
make -j4
make -j4 install
rm -rf $HOME/MOAB/moab $HOME/MOAB/build
popd

37
tools/ci/gha-install-dagmc.sh
View file

@ -2,34 +2,23 @@
#!/bin/bash
set -ex
# MOAB Variables
MOAB_BRANCH='5.5.1'
MOAB_REPO='https://bitbucket.org/fathomteam/moab/'
MOAB_INSTALL_DIR=$HOME/MOAB/
# DAGMC Variables
DAGMC_BRANCH='develop'
DAGMC_REPO='https://github.com/svalinn/dagmc'
DAGMC_INSTALL_DIR=$HOME/DAGMC/
CURRENT_DIR=$(pwd)
# MOAB Install
cd $HOME
mkdir MOAB && cd MOAB
git clone -b $MOAB_BRANCH $MOAB_REPO
mkdir build && cd build
cmake ../moab -DENABLE_HDF5=ON -DENABLE_NETCDF=ON -DBUILD_SHARED_LIBS=ON -DCMAKE_INSTALL_PREFIX=$MOAB_INSTALL_DIR
make -j && make -j install
rm -rf $HOME/MOAB/moab $HOME/MOAB/build
# DAGMC Install
cd $HOME
mkdir DAGMC && cd DAGMC
git clone -b $DAGMC_BRANCH $DAGMC_REPO
mkdir build && cd build
cmake ../dagmc -DBUILD_TALLY=ON -DCMAKE_INSTALL_PREFIX=$DAGMC_INSTALL_DIR -DBUILD_STATIC_LIBS=OFF -DMOAB_DIR=$MOAB_INSTALL_DIR
make -j install
pushd $HOME
mkdir -p DAGMC
cd DAGMC
git clone -b $DAGMC_BRANCH $DAGMC_REPO dagmc
mkdir build
cd build
cmake ../dagmc \
-DBUILD_TALLY=ON \
-DCMAKE_INSTALL_PREFIX=$DAGMC_INSTALL_DIR \
-DBUILD_STATIC_LIBS=OFF \
-DMOAB_DIR=$HOME/MOAB
make -j4 install
rm -rf $HOME/DAGMC/dagmc $HOME/DAGMC/build
cd $CURRENT_DIR
popd

43
tools/ci/gha-install-xdg.sh Executable file
View file

@ -0,0 +1,43 @@
#!/bin/bash
set -ex
XDG_BRANCH='main'
XDG_REPO='https://github.com/xdg-org/xdg.git'
XDG_INSTALL_DIR=$HOME/XDG/
pushd $HOME
mkdir -p XDG
cd XDG
git clone -b $XDG_BRANCH --recurse-submodules $XDG_REPO xdg
mkdir build
cd build
cmake_args=(
../xdg
-DCMAKE_INSTALL_PREFIX=$XDG_INSTALL_DIR
-DXDG_BUILD_TESTS=OFF
-DXDG_BUILD_TOOLS=ON
-DXDG_ENABLE_MOAB=ON
-DMOAB_DIR=$HOME/MOAB
)
if [[ $LIBMESH == 'y' || $XDG == 'y' ]]; then
cmake_args+=(
-DXDG_ENABLE_LIBMESH=ON
-DCMAKE_PREFIX_PATH=$HOME/LIBMESH
)
else
cmake_args+=(-DXDG_ENABLE_LIBMESH=OFF)
fi
if [[ $MPI == 'y' ]]; then
cmake_args+=(-DXDG_LINK_MPI=ON)
fi
cmake "${cmake_args[@]}"
make -j4
make -j4 install
rm -rf $HOME/XDG/xdg $HOME/XDG/build
popd

22
tools/ci/gha-install.py
View file

@ -3,7 +3,8 @@ import shutil
import subprocess
def install(omp=False, mpi=False, phdf5=False, dagmc=False, libmesh=False):
def install(omp=False, mpi=False, phdf5=False, dagmc=False, xdg=False,
libmesh=False):
# Create build directory and change to it
shutil.rmtree('build', ignore_errors=True)
os.mkdir('build')
@ -29,16 +30,26 @@ def install(omp=False, mpi=False, phdf5=False, dagmc=False, libmesh=False):
else:
cmake_cmd.append('-DHDF5_PREFER_PARALLEL=OFF')
prefix_paths = []
if dagmc:
cmake_cmd.append('-DOPENMC_USE_DAGMC=ON')
cmake_cmd.append('-DOPENMC_USE_UWUW=ON')
dagmc_path = os.environ.get('HOME') + '/DAGMC'
cmake_cmd.append('-DCMAKE_PREFIX_PATH=' + dagmc_path)
prefix_paths.append(dagmc_path)
if libmesh:
if xdg:
cmake_cmd.append('-DOPENMC_USE_XDG=ON')
xdg_path = os.environ.get('HOME') + '/XDG'
prefix_paths.append(xdg_path)
if libmesh or xdg:
cmake_cmd.append('-DOPENMC_USE_LIBMESH=ON')
libmesh_path = os.environ.get('HOME') + '/LIBMESH'
cmake_cmd.append('-DCMAKE_PREFIX_PATH=' + libmesh_path)
prefix_paths.append(libmesh_path)
if prefix_paths:
cmake_cmd.append('-DCMAKE_PREFIX_PATH=' + ';'.join(prefix_paths))
# Build in coverage mode for coverage testing
cmake_cmd.append('-DOPENMC_ENABLE_COVERAGE=on')
@ -59,10 +70,11 @@ def main():
mpi = (os.environ.get('MPI') == 'y')
phdf5 = (os.environ.get('PHDF5') == 'y')
dagmc = (os.environ.get('DAGMC') == 'y')
xdg = (os.environ.get('XDG') == 'y')
libmesh = (os.environ.get('LIBMESH') == 'y')
# Build and install
install(omp, mpi, phdf5, dagmc, libmesh)
install(omp, mpi, phdf5, dagmc, xdg, libmesh)
if __name__ == '__main__':
main()

18
tools/ci/gha-install.sh
View file

@ -9,20 +9,30 @@ pip install --upgrade numpy
# Install NJOY 2016
./tools/ci/gha-install-njoy.sh
# Install DAGMC if needed
if [[ $DAGMC = 'y' ]]; then
./tools/ci/gha-install-dagmc.sh
# Build MOAB if needed
if [[ $DAGMC = 'y' || $XDG = 'y' ]]; then
./tools/ci/gha-build-moab.sh
fi
# Install NCrystal and verify installation
pip install 'ncrystal>=4.1.0'
nctool --test
# Install DAGMC if needed
if [[ $DAGMC = 'y' ]]; then
./tools/ci/gha-install-dagmc.sh
fi
# Install libMesh if needed
if [[ $LIBMESH = 'y' ]]; then
if [[ $LIBMESH = 'y' || $XDG = 'y' ]]; then
./tools/ci/gha-install-libmesh.sh
fi
# Install XDG if needed
if [[ $XDG = 'y' ]]; then
./tools/ci/gha-install-xdg.sh
fi
# Install MCPL
pip install mcpl