Storing surface source points using a cell ID (#2888)

Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
This commit is contained in:
Joffrey Dorville 2024-06-19 10:11:58 -05:00 committed by GitHub
parent 84f561c1ed
commit ddc9526966
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120 changed files with 3963 additions and 86 deletions

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@ -902,7 +902,12 @@ attributes/sub-elements:
The ``<surf_source_write>`` element triggers OpenMC to bank particles crossing
certain surfaces and write out the source bank in a separate file called
``surface_source.h5``. This element has the following attributes/sub-elements:
``surface_source.h5``. One or multiple surface IDs and one cell ID can be used
to select the surfaces of interest. If no surface IDs are declared, every surface
of the model is eligible to bank particles. In that case, a cell ID (using
either the ``cell``, ``cellfrom`` or ``cellto`` attributes) can be used to select
every surface of a specific cell. This element has the following
attributes/sub-elements:
:surface_ids:
A list of integers separated by spaces indicating the unique IDs of surfaces
@ -928,6 +933,34 @@ certain surfaces and write out the source bank in a separate file called
.. _MCPL: https://mctools.github.io/mcpl/mcpl.pdf
:cell:
An integer representing the cell ID used to determine if particles crossing
identified surfaces are to be banked. Particles coming from or going to this
declared cell will be banked if they cross the identified surfaces.
*Default*: None
:cellfrom:
An integer representing the cell ID used to determine if particles crossing
identified surfaces are to be banked. Particles coming from this declared
cell will be banked if they cross the identified surfaces.
*Default*: None
:cellto:
An integer representing the cell ID used to determine if particles crossing
identified surfaces are to be banked. Particles going to this declared cell
will be banked if they cross the identified surfaces.
*Default*: None
.. note:: The ``cell``, ``cellfrom`` and ``cellto`` attributes cannot be
used simultaneously.
.. note:: Surfaces with boundary conditions that are not "transmission" or "vacuum"
are not eligible to store any particles when using ``cell``, ``cellfrom``
or ``cellto`` attributes. It is recommended to use surface IDs instead.
------------------------------
``<survival_biasing>`` Element
------------------------------

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@ -277,6 +277,9 @@ source file can be manually generated with the :func:`openmc.write_source_file`
function. This is particularly useful for coupling OpenMC with another program
that generates a source to be used in OpenMC.
Surface Sources
+++++++++++++++
A source file based on particles that cross one or more surfaces can be
generated during a simulation using the :attr:`Settings.surf_source_write`
attribute::
@ -287,7 +290,51 @@ attribute::
}
In this example, at most 10,000 source particles are stored when particles cross
surfaces with IDs of 1, 2, or 3.
surfaces with IDs of 1, 2, or 3. If no surface IDs are declared, particles
crossing any surface of the model will be banked::
settings.surf_source_write = {'max_particles': 10000}
A cell ID can also be used to bank particles that are crossing any surface of
a cell that particles are either coming from or going to::
settings.surf_source_write = {'cell': 1, 'max_particles': 10000}
In this example, particles that are crossing any surface that bounds cell 1 will
be banked excluding any surface that does not use a 'transmission' or 'vacuum'
boundary condition.
.. note:: Surfaces with boundary conditions that are not "transmission" or "vacuum"
are not eligible to store any particles when using ``cell``, ``cellfrom``
or ``cellto`` attributes. It is recommended to use surface IDs instead.
Surface IDs can be used in combination with a cell ID::
settings.surf_source_write = {
'cell': 1,
'surfaces_ids': [1, 2, 3],
'max_particles': 10000
}
In that case, only particles that are crossing the declared surfaces coming from
cell 1 or going to cell 1 will be banked. To account specifically for particles
leaving or entering a given cell, ``cellfrom`` and ``cellto`` are also available
to respectively account for particles coming from a cell::
settings.surf_source_write = {
'cellfrom': 1,
'max_particles': 10000
}
or particles going to a cell::
settings.surf_source_write = {
'cellto': 1,
'max_particles': 10000
}
.. note:: The ``cell``, ``cellfrom`` and ``cellto`` attributes cannot be
used simultaneously.
.. _compiled_source:

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@ -74,7 +74,7 @@ public:
void pht_secondary_particles();
//! Cross a surface and handle boundary conditions
void cross_surface();
void cross_surface(const Surface& surf);
//! Cross a vacuum boundary condition.
//
@ -127,6 +127,8 @@ std::string particle_type_to_str(ParticleType type);
ParticleType str_to_particle_type(std::string str);
void add_surf_source_to_bank(Particle& p, const Surface& surf);
} // namespace openmc
#endif // OPENMC_PARTICLE_H

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@ -211,9 +211,15 @@ public:
// resets all coordinate levels for the particle
void clear()
{
for (auto& level : coord_)
for (auto& level : coord_) {
level.reset();
}
n_coord_ = 1;
for (auto& cell : cell_last_) {
cell = C_NONE;
}
n_coord_last_ = 1;
}
// Initialize all internal state from position and direction

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@ -16,6 +16,14 @@
namespace openmc {
// Type of surface source write
enum class SSWCellType {
None,
Both,
From,
To,
};
//==============================================================================
// Global variable declarations
//==============================================================================
@ -125,6 +133,10 @@ extern int
max_history_splits; //!< maximum number of particle splits for weight windows
extern int64_t max_surface_particles; //!< maximum number of particles to be
//!< banked on surfaces per process
extern int64_t ssw_cell_id; //!< Cell id for the surface source
//!< write setting
extern SSWCellType ssw_cell_type; //!< Type of option for the cell
//!< argument of surface source write
extern TemperatureMethod
temperature_method; //!< method for choosing temperatures
extern double

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@ -201,6 +201,15 @@ class Settings:
:max_particles: Maximum number of particles to be banked on surfaces per
process (int)
:mcpl: Output in the form of an MCPL-file (bool)
:cell: Cell ID used to determine if particles crossing identified
surfaces are to be banked. Particles coming from or going to this
declared cell will be banked (int)
:cellfrom: Cell ID used to determine if particles crossing identified
surfaces are to be banked. Particles coming from this
declared cell will be banked (int)
:cellto: Cell ID used to determine if particles crossing identified
surfaces are to be banked. Particles going to this declared
cell will be banked (int)
survival_biasing : bool
Indicate whether survival biasing is to be used
tabular_legendre : dict
@ -693,23 +702,30 @@ class Settings:
@surf_source_write.setter
def surf_source_write(self, surf_source_write: dict):
cv.check_type('surface source writing options', surf_source_write, Mapping)
cv.check_type("surface source writing options", surf_source_write, Mapping)
for key, value in surf_source_write.items():
cv.check_value('surface source writing key', key,
('surface_ids', 'max_particles', 'mcpl'))
if key == 'surface_ids':
cv.check_type('surface ids for source banking', value,
Iterable, Integral)
cv.check_value(
"surface source writing key",
key,
("surface_ids", "max_particles", "mcpl", "cell", "cellfrom", "cellto"),
)
if key == "surface_ids":
cv.check_type(
"surface ids for source banking", value, Iterable, Integral
)
for surf_id in value:
cv.check_greater_than('surface id for source banking',
surf_id, 0)
elif key == 'max_particles':
cv.check_type('maximum particle banks on surfaces per process',
value, Integral)
cv.check_greater_than('maximum particle banks on surfaces per process',
value, 0)
elif key == 'mcpl':
cv.check_type('write to an MCPL-format file', value, bool)
cv.check_greater_than("surface id for source banking", surf_id, 0)
elif key == "mcpl":
cv.check_type("write to an MCPL-format file", value, bool)
elif key in ("max_particles", "cell", "cellfrom", "cellto"):
name = {
"max_particles": "maximum particle banks on surfaces per process",
"cell": "Cell ID for source banking (from or to)",
"cellfrom": "Cell ID for source banking (from only)",
"cellto": "Cell ID for source banking (to only)",
}[key]
cv.check_type(name, value, Integral)
cv.check_greater_than(name, value, 0)
self._surf_source_write = surf_source_write
@ -1207,16 +1223,18 @@ class Settings:
def _create_surf_source_write_subelement(self, root):
if self._surf_source_write:
element = ET.SubElement(root, "surf_source_write")
if 'surface_ids' in self._surf_source_write:
if "surface_ids" in self._surf_source_write:
subelement = ET.SubElement(element, "surface_ids")
subelement.text = ' '.join(
str(x) for x in self._surf_source_write['surface_ids'])
if 'max_particles' in self._surf_source_write:
subelement = ET.SubElement(element, "max_particles")
subelement.text = str(self._surf_source_write['max_particles'])
if 'mcpl' in self._surf_source_write:
subelement.text = " ".join(
str(x) for x in self._surf_source_write["surface_ids"]
)
if "mcpl" in self._surf_source_write:
subelement = ET.SubElement(element, "mcpl")
subelement.text = str(self._surf_source_write['mcpl']).lower()
subelement.text = str(self._surf_source_write["mcpl"]).lower()
for key in ("max_particles", "cell", "cellfrom", "cellto"):
if key in self._surf_source_write:
subelement = ET.SubElement(element, key)
subelement.text = str(self._surf_source_write[key])
def _create_confidence_intervals(self, root):
if self._confidence_intervals is not None:
@ -1381,9 +1399,9 @@ class Settings:
elem.text = str(self._create_fission_neutrons).lower()
def _create_create_delayed_neutrons_subelement(self, root):
if self._create_delayed_neutrons is not None:
elem = ET.SubElement(root, "create_delayed_neutrons")
elem.text = str(self._create_delayed_neutrons).lower()
if self._create_delayed_neutrons is not None:
elem = ET.SubElement(root, "create_delayed_neutrons")
elem.text = str(self._create_delayed_neutrons).lower()
def _create_delayed_photon_scaling_subelement(self, root):
if self._delayed_photon_scaling is not None:
@ -1610,17 +1628,18 @@ class Settings:
def _surf_source_write_from_xml_element(self, root):
elem = root.find('surf_source_write')
if elem is not None:
for key in ('surface_ids', 'max_particles','mcpl'):
value = get_text(elem, key)
if value is not None:
if key == 'surface_ids':
value = [int(x) for x in value.split()]
elif key in ('max_particles'):
value = int(value)
elif key == 'mcpl':
value = value in ('true', '1')
self.surf_source_write[key] = value
if elem is None:
return
for key in ('surface_ids', 'max_particles', 'mcpl', 'cell', 'cellto', 'cellfrom'):
value = get_text(elem, key)
if value is not None:
if key == 'surface_ids':
value = [int(x) for x in value.split()]
elif key == 'mcpl':
value = value in ('true', '1')
elif key in ('max_particles', 'cell', 'cellfrom', 'cellto'):
value = int(value)
self.surf_source_write[key] = value
def _confidence_intervals_from_xml_element(self, root):
text = get_text(root, 'confidence_intervals')

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@ -271,8 +271,10 @@ void DAGUniverse::init_geometry()
: dagmc_instance_->id_by_index(2, i + 1);
// set surface source attribute if needed
if (contains(settings::source_write_surf_id, s->id_))
if (contains(settings::source_write_surf_id, s->id_) ||
settings::source_write_surf_id.empty()) {
s->surf_source_ = true;
}
// set BCs
std::string bc_value =

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@ -168,6 +168,12 @@ void Particle::event_calculate_xs()
// Set birth cell attribute
if (cell_born() == C_NONE)
cell_born() = lowest_coord().cell;
// Initialize last cells from current cell
for (int j = 0; j < n_coord(); ++j) {
cell_last(j) = coord(j).cell;
}
n_coord_last() = n_coord();
}
// Write particle track.
@ -264,16 +270,16 @@ void Particle::event_advance()
void Particle::event_cross_surface()
{
// Set surface that particle is on and adjust coordinate levels
surface() = boundary().surface_index;
n_coord() = boundary().coord_level;
// Saving previous cell data
for (int j = 0; j < n_coord(); ++j) {
cell_last(j) = coord(j).cell;
}
n_coord_last() = n_coord();
// Set surface that particle is on and adjust coordinate levels
surface() = boundary().surface_index;
n_coord() = boundary().coord_level;
if (boundary().lattice_translation[0] != 0 ||
boundary().lattice_translation[1] != 0 ||
boundary().lattice_translation[2] != 0) {
@ -284,7 +290,17 @@ void Particle::event_cross_surface()
event() = TallyEvent::LATTICE;
} else {
// Particle crosses surface
cross_surface();
// TODO: off-by-one
const auto& surf {model::surfaces[std::abs(surface()) - 1].get()};
// If BC, add particle to surface source before crossing surface
if (surf->surf_source_ && surf->bc_) {
add_surf_source_to_bank(*this, *surf);
}
cross_surface(*surf);
// If no BC, add particle to surface source after crossing surface
if (surf->surf_source_ && !surf->bc_) {
add_surf_source_to_bank(*this, *surf);
}
if (settings::weight_window_checkpoint_surface) {
apply_weight_windows(*this);
}
@ -418,6 +434,12 @@ void Particle::event_revive_from_secondary()
// Set birth cell attribute
if (cell_born() == C_NONE)
cell_born() = lowest_coord().cell;
// Initialize last cells from current cell
for (int j = 0; j < n_coord(); ++j) {
cell_last(j) = coord(j).cell;
}
n_coord_last() = n_coord();
}
pht_secondary_particles();
}
@ -502,40 +524,22 @@ void Particle::pht_secondary_particles()
}
}
void Particle::cross_surface()
void Particle::cross_surface(const Surface& surf)
{
int i_surface = std::abs(surface());
// TODO: off-by-one
const auto& surf {model::surfaces[i_surface - 1].get()};
if (settings::verbosity >= 10 || trace()) {
write_message(1, " Crossing surface {}", surf->id_);
}
if (surf->surf_source_ && simulation::current_batch > settings::n_inactive &&
!simulation::surf_source_bank.full()) {
SourceSite site;
site.r = r();
site.u = u();
site.E = E();
site.time = time();
site.wgt = wgt();
site.delayed_group = delayed_group();
site.surf_id = surf->id_;
site.particle = type();
site.parent_id = id();
site.progeny_id = n_progeny();
int64_t idx = simulation::surf_source_bank.thread_safe_append(site);
if (settings::verbosity >= 10 || trace()) {
write_message(1, " Crossing surface {}", surf.id_);
}
// if we're crossing a CSG surface, make sure the DAG history is reset
#ifdef DAGMC
if (surf->geom_type_ == GeometryType::CSG)
if (surf.geom_type_ == GeometryType::CSG)
history().reset();
#endif
// Handle any applicable boundary conditions.
if (surf->bc_ && settings::run_mode != RunMode::PLOTTING) {
surf->bc_->handle_particle(*this, *surf);
if (surf.bc_ && settings::run_mode != RunMode::PLOTTING) {
surf.bc_->handle_particle(*this, surf);
return;
}
@ -544,10 +548,10 @@ void Particle::cross_surface()
#ifdef DAGMC
// in DAGMC, we know what the next cell should be
if (surf->geom_type_ == GeometryType::DAG) {
int32_t i_cell =
next_cell(i_surface, cell_last(n_coord() - 1), lowest_coord().universe) -
1;
if (surf.geom_type_ == GeometryType::DAG) {
int32_t i_cell = next_cell(std::abs(surface()), cell_last(n_coord() - 1),
lowest_coord().universe) -
1;
// save material and temp
material_last() = material();
sqrtkT_last() = sqrtkT();
@ -561,8 +565,9 @@ void Particle::cross_surface()
#endif
bool verbose = settings::verbosity >= 10 || trace();
if (neighbor_list_find_cell(*this, verbose))
if (neighbor_list_find_cell(*this, verbose)) {
return;
}
// ==========================================================================
// COULDN'T FIND PARTICLE IN NEIGHBORING CELLS, SEARCH ALL CELLS
@ -586,7 +591,7 @@ void Particle::cross_surface()
if (!exhaustive_find_cell(*this, verbose)) {
mark_as_lost("After particle " + std::to_string(id()) +
" crossed surface " + std::to_string(surf->id_) +
" crossed surface " + std::to_string(surf.id_) +
" it could not be located in any cell and it did not leak.");
return;
}
@ -650,7 +655,7 @@ void Particle::cross_reflective_bc(const Surface& surf, Direction new_u)
u() = new_u;
// Reassign particle's cell and surface
coord(0).cell = cell_last(n_coord_last() - 1);
coord(0).cell = cell_last(0);
surface() = -surface();
// If a reflective surface is coincident with a lattice or universe
@ -873,4 +878,90 @@ ParticleType str_to_particle_type(std::string str)
}
}
void add_surf_source_to_bank(Particle& p, const Surface& surf)
{
if (simulation::current_batch <= settings::n_inactive ||
simulation::surf_source_bank.full()) {
return;
}
// If a cell/cellfrom/cellto parameter is defined
if (settings::ssw_cell_id != C_NONE) {
// Retrieve cell index and storage type
int cell_idx = model::cell_map[settings::ssw_cell_id];
if (surf.bc_) {
// Leave if cellto with vacuum boundary condition
if (surf.bc_->type() == "vacuum" &&
settings::ssw_cell_type == SSWCellType::To) {
return;
}
// Leave if other boundary condition than vacuum
if (surf.bc_->type() != "vacuum") {
return;
}
}
// Check if the cell of interest has been exited
bool exited = false;
for (int i = 0; i < p.n_coord_last(); ++i) {
if (p.cell_last(i) == cell_idx) {
exited = true;
}
}
// Check if the cell of interest has been entered
bool entered = false;
for (int i = 0; i < p.n_coord(); ++i) {
if (p.coord(i).cell == cell_idx) {
entered = true;
}
}
// Vacuum boundary conditions: return if cell is not exited
if (surf.bc_) {
if (surf.bc_->type() == "vacuum" && !exited) {
return;
}
} else {
// If we both enter and exit the cell of interest
if (entered && exited) {
return;
}
// If we did not enter nor exit the cell of interest
if (!entered && !exited) {
return;
}
// If cellfrom and the cell before crossing is not the cell of
// interest
if (settings::ssw_cell_type == SSWCellType::From && !exited) {
return;
}
// If cellto and the cell after crossing is not the cell of interest
if (settings::ssw_cell_type == SSWCellType::To && !entered) {
return;
}
}
}
SourceSite site;
site.r = p.r();
site.u = p.u();
site.E = p.E();
site.time = p.time();
site.wgt = p.wgt();
site.delayed_group = p.delayed_group();
site.surf_id = surf.id_;
site.particle = p.type();
site.parent_id = p.id();
site.progeny_id = p.n_progeny();
int64_t idx = simulation::surf_source_bank.thread_safe_append(site);
}
} // namespace openmc

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@ -119,6 +119,8 @@ std::unordered_set<int> sourcepoint_batch;
std::unordered_set<int> statepoint_batch;
std::unordered_set<int> source_write_surf_id;
int64_t max_surface_particles;
int64_t ssw_cell_id {C_NONE};
SSWCellType ssw_cell_type {SSWCellType::None};
TemperatureMethod temperature_method {TemperatureMethod::NEAREST};
double temperature_tolerance {10.0};
double temperature_default {293.6};
@ -747,7 +749,9 @@ void read_settings_xml(pugi::xml_node root)
// Get surface source write node
xml_node node_ssw = root.child("surf_source_write");
// Determine surface ids at which crossing particles are to be banked
// Determine surface ids at which crossing particles are to be banked.
// If no surfaces are specified, all surfaces in the model will be used
// to bank source points.
if (check_for_node(node_ssw, "surface_ids")) {
auto temp = get_node_array<int>(node_ssw, "surface_ids");
for (const auto& b : temp) {
@ -759,7 +763,12 @@ void read_settings_xml(pugi::xml_node root)
if (check_for_node(node_ssw, "max_particles")) {
max_surface_particles =
std::stoll(get_node_value(node_ssw, "max_particles"));
} else {
fatal_error("A maximum number of particles needs to be specified "
"using the 'max_particles' parameter to store surface "
"source points.");
}
if (check_for_node(node_ssw, "mcpl")) {
surf_mcpl_write = get_node_value_bool(node_ssw, "mcpl");
@ -769,6 +778,27 @@ void read_settings_xml(pugi::xml_node root)
"surface source files.");
}
}
// Get cell information
if (check_for_node(node_ssw, "cell")) {
ssw_cell_id = std::stoll(get_node_value(node_ssw, "cell"));
ssw_cell_type = SSWCellType::Both;
}
if (check_for_node(node_ssw, "cellfrom")) {
if (ssw_cell_id != C_NONE) {
fatal_error(
"'cell', 'cellfrom' and 'cellto' cannot be used at the same time.");
}
ssw_cell_id = std::stoll(get_node_value(node_ssw, "cellfrom"));
ssw_cell_type = SSWCellType::From;
}
if (check_for_node(node_ssw, "cellto")) {
if (ssw_cell_id != C_NONE) {
fatal_error(
"'cell', 'cellfrom' and 'cellto' cannot be used at the same time.");
}
ssw_cell_id = std::stoll(get_node_value(node_ssw, "cellto"));
ssw_cell_type = SSWCellType::To;
}
}
// If source is not separate and is to be written out in the statepoint file,

View file

@ -63,7 +63,8 @@ Surface::Surface(pugi::xml_node surf_node)
{
if (check_for_node(surf_node, "id")) {
id_ = std::stoi(get_node_value(surf_node, "id"));
if (contains(settings::source_write_surf_id, id_)) {
if (contains(settings::source_write_surf_id, id_) ||
settings::source_write_surf_id.empty()) {
surf_source_ = true;
}
} else {

View file

@ -0,0 +1,151 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.97"/>
<nuclide ao="0.0004524" name="U234"/>
<nuclide ao="0.0506068" name="U235"/>
<nuclide ao="0.948709" name="U238"/>
<nuclide ao="0.0002318" name="U236"/>
<nuclide ao="2.0" name="O16"/>
</material>
<material id="2">
<density units="g/cm3" value="1.0"/>
<nuclide ao="2.0" name="H1"/>
<nuclide ao="1.0" name="O16"/>
</material>
<material id="3">
<density units="g/cm3" value="0.001225"/>
<nuclide ao="0.1999242" name="O16"/>
<nuclide ao="7.58e-05" name="O17"/>
<nuclide ao="0.7970696" name="N14"/>
<nuclide ao="0.0029304" name="N15"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3" universe="1"/>
<cell id="2" material="3" region="1 | -2 | 3" universe="1"/>
<cell fill="1" id="3" region="-5 4 -7 6 -9 8" universe="2"/>
<cell id="4" material="2" region="-11 10 -13 12 -15 14 (5 | -4 | 7 | -6 | 9 | -8)" universe="2"/>
<surface coeffs="0.0 0.0 2.0" id="1" type="z-cylinder"/>
<surface coeffs="-2.0" id="2" type="z-plane"/>
<surface coeffs="2.0" id="3" type="z-plane"/>
<surface coeffs="-2.05" id="4" type="x-plane"/>
<surface coeffs="2.05" id="5" type="x-plane"/>
<surface coeffs="-2.05" id="6" type="y-plane"/>
<surface coeffs="2.05" id="7" type="y-plane"/>
<surface coeffs="-2.05" id="8" type="z-plane"/>
<surface coeffs="2.05" id="9" type="z-plane"/>
<surface boundary="vacuum" coeffs="-6.0" id="10" type="x-plane"/>
<surface boundary="vacuum" coeffs="6.0" id="11" type="x-plane"/>
<surface boundary="vacuum" coeffs="-6.0" id="12" type="y-plane"/>
<surface boundary="vacuum" coeffs="6.0" id="13" type="y-plane"/>
<surface boundary="vacuum" coeffs="-6.0" id="14" type="z-plane"/>
<surface boundary="vacuum" coeffs="6.0" id="15" type="z-plane"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>2000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source particle="neutron" strength="1.0" type="independent">
<space type="fission">
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
</space>
</source>
<seed>1</seed>
</settings>
<tallies>
<filter id="5" type="cellfrom">
<bins>1</bins>
</filter>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>2</bins>
</filter>
<filter id="3" type="cell">
<bins>3</bins>
</filter>
<filter id="4" type="cell">
<bins>4</bins>
</filter>
<filter id="6" type="cellfrom">
<bins>2</bins>
</filter>
<filter id="7" type="cellfrom">
<bins>3</bins>
</filter>
<filter id="8" type="cellfrom">
<bins>4</bins>
</filter>
<tally id="1" name="total from 1 in 1">
<filters>5 1</filters>
<scores>total</scores>
</tally>
<tally id="2" name="total from 1 in 2">
<filters>5 2</filters>
<scores>total</scores>
</tally>
<tally id="3" name="total from 1 in 3">
<filters>5 3</filters>
<scores>total</scores>
</tally>
<tally id="4" name="total from 1 in 4">
<filters>5 4</filters>
<scores>total</scores>
</tally>
<tally id="5" name="total from 2 in 1">
<filters>6 1</filters>
<scores>total</scores>
</tally>
<tally id="6" name="total from 2 in 2">
<filters>6 2</filters>
<scores>total</scores>
</tally>
<tally id="7" name="total from 2 in 3">
<filters>6 3</filters>
<scores>total</scores>
</tally>
<tally id="8" name="total from 2 in 4">
<filters>6 4</filters>
<scores>total</scores>
</tally>
<tally id="9" name="total from 3 in 1">
<filters>7 1</filters>
<scores>total</scores>
</tally>
<tally id="10" name="total from 3 in 2">
<filters>7 2</filters>
<scores>total</scores>
</tally>
<tally id="11" name="total from 3 in 3">
<filters>7 3</filters>
<scores>total</scores>
</tally>
<tally id="12" name="total from 3 in 4">
<filters>7 4</filters>
<scores>total</scores>
</tally>
<tally id="13" name="total from 4 in 1">
<filters>8 1</filters>
<scores>total</scores>
</tally>
<tally id="14" name="total from 4 in 2">
<filters>8 2</filters>
<scores>total</scores>
</tally>
<tally id="15" name="total from 4 in 3">
<filters>8 3</filters>
<scores>total</scores>
</tally>
<tally id="16" name="total from 4 in 4">
<filters>8 4</filters>
<scores>total</scores>
</tally>
<tally id="17" name="total">
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -0,0 +1,53 @@
k-combined:
9.640806E-02 2.655206E-03
tally 1:
6.025999E+00
3.635317E+00
tally 2:
4.523606E-04
2.051522E-08
tally 3:
6.026452E+00
3.635862E+00
tally 4:
0.000000E+00
0.000000E+00
tally 5:
1.530903E+00
2.357048E-01
tally 6:
4.992646E-05
2.600391E-10
tally 7:
1.530953E+00
2.357201E-01
tally 8:
1.889115E+01
3.574727E+01
tally 9:
7.556902E+00
5.717680E+00
tally 10:
5.022871E-04
2.531352E-08
tally 11:
7.557405E+00
5.718440E+00
tally 12:
1.889115E+01
3.574727E+01
tally 13:
0.000000E+00
0.000000E+00
tally 14:
2.663407E-04
7.161725E-09
tally 15:
2.663407E-04
7.161725E-09
tally 16:
8.025710E+01
6.459305E+02
tally 17:
1.067059E+02
1.140939E+03

View file

@ -0,0 +1,315 @@
"""This test ensures that the CellFromFilter works correctly even if the level of
coordinates (number of encapsulated universes) is different in the cell from
where the particle originates compared to the cell where the particle is going.
A matrix of reaction rates based on where the particle is coming from and
where it goes to is calculated and compared to the total reaction rate of the problem.
The components of this matrix are also compared to other components using symmetric
properties.
TODO:
- Test with a lattice,
- Test with mesh,
- Test with reflective boundary conditions,
- Test with periodic boundary conditions.
"""
from numpy.testing import assert_allclose, assert_equal
import numpy as np
import openmc
import pytest
from tests.testing_harness import PyAPITestHarness
RTOL = 1.0e-7
ATOL = 0.0
@pytest.fixture
def model():
"""Cylindrical core contained in a first box which is contained in a larger box.
A lower universe is used to describe the interior of the first box which
contains the core and its surrounding space."""
openmc.reset_auto_ids()
model = openmc.Model()
# =============================================================================
# Materials
# =============================================================================
fuel = openmc.Material()
fuel.add_nuclide("U234", 0.0004524)
fuel.add_nuclide("U235", 0.0506068)
fuel.add_nuclide("U238", 0.9487090)
fuel.add_nuclide("U236", 0.0002318)
fuel.add_nuclide("O16", 2.0)
fuel.set_density("g/cm3", 10.97)
water = openmc.Material()
water.add_nuclide("H1", 2.0)
water.add_nuclide("O16", 1.0)
water.set_density("g/cm3", 1.0)
air = openmc.Material()
air.add_element("O", 0.2)
air.add_element("N", 0.8)
air.set_density("g/cm3", 0.001225)
# =============================================================================
# Geometry
# =============================================================================
# -----------------------------------------------------------------------------
# Cylindrical core
# -----------------------------------------------------------------------------
# Parameters
core_radius = 2.0
core_height = 4.0
# Surfaces
core_cylinder = openmc.ZCylinder(r=core_radius)
core_lower_plane = openmc.ZPlane(z0=-core_height / 2.0)
core_upper_plane = openmc.ZPlane(z0=core_height / 2.0)
# Region
core_region = -core_cylinder & +core_lower_plane & -core_upper_plane
# Cells
core = openmc.Cell(fill=fuel, region=core_region)
outside_core_region = +core_cylinder | -core_lower_plane | +core_upper_plane
outside_core = openmc.Cell(fill=air, region=outside_core_region)
# Universe
inside_box1_universe = openmc.Universe(cells=[core, outside_core])
# -----------------------------------------------------------------------------
# Box 1
# -----------------------------------------------------------------------------
# Parameters
box1_size = 4.1
# Surfaces
box1_rpp = openmc.model.RectangularParallelepiped(
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
-box1_size / 2.0, box1_size / 2.0,
)
# Cell
box1 = openmc.Cell(fill=inside_box1_universe, region=-box1_rpp)
# -----------------------------------------------------------------------------
# Box 2
# -----------------------------------------------------------------------------
# Parameters
box2_size = 12
# Surfaces
box2_rpp = openmc.model.RectangularParallelepiped(
-box2_size / 2.0, box2_size / 2.0,
-box2_size / 2.0, box2_size / 2.0,
-box2_size / 2.0, box2_size / 2.0,
boundary_type="vacuum"
)
# Cell
box2 = openmc.Cell(fill=water, region=-box2_rpp & +box1_rpp)
# Register geometry
model.geometry = openmc.Geometry([box1, box2])
# =============================================================================
# Settings
# =============================================================================
model.settings = openmc.Settings()
model.settings.particles = 2000
model.settings.batches = 15
model.settings.inactive = 5
model.settings.seed = 1
bounds = [
-core_radius,
-core_radius,
-core_height / 2.0,
core_radius,
core_radius,
core_height / 2.0,
]
distribution = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
model.settings.source = openmc.IndependentSource(space=distribution)
# =============================================================================
# Tallies
# =============================================================================
in_core_filter = openmc.CellFilter([core])
in_outside_core_filter = openmc.CellFilter([outside_core])
in_box1_filter = openmc.CellFilter([box1])
in_box2_filter = openmc.CellFilter([box2])
from_core_filter = openmc.CellFromFilter([core])
from_outside_core_filter = openmc.CellFromFilter([outside_core])
from_box1_filter = openmc.CellFromFilter([box1])
from_box2_filter = openmc.CellFromFilter([box2])
t1_1 = openmc.Tally(name="total from 1 in 1")
t1_1.filters = [from_core_filter, in_core_filter]
t1_1.scores = ["total"]
t1_2 = openmc.Tally(name="total from 1 in 2")
t1_2.filters = [from_core_filter, in_outside_core_filter]
t1_2.scores = ["total"]
t1_3 = openmc.Tally(name="total from 1 in 3")
t1_3.filters = [from_core_filter, in_box1_filter]
t1_3.scores = ["total"]
t1_4 = openmc.Tally(name="total from 1 in 4")
t1_4.filters = [from_core_filter, in_box2_filter]
t1_4.scores = ["total"]
t2_1 = openmc.Tally(name="total from 2 in 1")
t2_1.filters = [from_outside_core_filter, in_core_filter]
t2_1.scores = ["total"]
t2_2 = openmc.Tally(name="total from 2 in 2")
t2_2.filters = [from_outside_core_filter, in_outside_core_filter]
t2_2.scores = ["total"]
t2_3 = openmc.Tally(name="total from 2 in 3")
t2_3.filters = [from_outside_core_filter, in_box1_filter]
t2_3.scores = ["total"]
t2_4 = openmc.Tally(name="total from 2 in 4")
t2_4.filters = [from_outside_core_filter, in_box2_filter]
t2_4.scores = ["total"]
t3_1 = openmc.Tally(name="total from 3 in 1")
t3_1.filters = [from_box1_filter, in_core_filter]
t3_1.scores = ["total"]
t3_2 = openmc.Tally(name="total from 3 in 2")
t3_2.filters = [from_box1_filter, in_outside_core_filter]
t3_2.scores = ["total"]
t3_3 = openmc.Tally(name="total from 3 in 3")
t3_3.filters = [from_box1_filter, in_box1_filter]
t3_3.scores = ["total"]
t3_4 = openmc.Tally(name="total from 3 in 4")
t3_4.filters = [from_box1_filter, in_box2_filter]
t3_4.scores = ["total"]
t4_1 = openmc.Tally(name="total from 4 in 1")
t4_1.filters = [from_box2_filter, in_core_filter]
t4_1.scores = ["total"]
t4_2 = openmc.Tally(name="total from 4 in 2")
t4_2.filters = [from_box2_filter, in_outside_core_filter]
t4_2.scores = ["total"]
t4_3 = openmc.Tally(name="total from 4 in 3")
t4_3.filters = [from_box2_filter, in_box1_filter]
t4_3.scores = ["total"]
t4_4 = openmc.Tally(name="total from 4 in 4")
t4_4.filters = [from_box2_filter, in_box2_filter]
t4_4.scores = ["total"]
tglobal = openmc.Tally(name="total")
tglobal.scores = ["total"]
model.tallies += [
t1_1,
t1_2,
t1_3,
t1_4,
t2_1,
t2_2,
t2_3,
t2_4,
t3_1,
t3_2,
t3_3,
t3_4,
t4_1,
t4_2,
t4_3,
t4_4,
tglobal,
]
return model
class CellFromFilterTest(PyAPITestHarness):
def _compare_results(self):
"""Additional unit tests on the tally results to check
consistency of CellFromFilter."""
with openmc.StatePoint(self.statepoint_name) as sp:
t1_1 = sp.get_tally(name="total from 1 in 1").mean
t1_2 = sp.get_tally(name="total from 1 in 2").mean
t1_3 = sp.get_tally(name="total from 1 in 3").mean
t1_4 = sp.get_tally(name="total from 1 in 4").mean
t2_1 = sp.get_tally(name="total from 2 in 1").mean
t2_2 = sp.get_tally(name="total from 2 in 2").mean
t2_3 = sp.get_tally(name="total from 2 in 3").mean
t2_4 = sp.get_tally(name="total from 2 in 4").mean
t3_1 = sp.get_tally(name="total from 3 in 1").mean
t3_2 = sp.get_tally(name="total from 3 in 2").mean
t3_3 = sp.get_tally(name="total from 3 in 3").mean
t3_4 = sp.get_tally(name="total from 3 in 4").mean
t4_1 = sp.get_tally(name="total from 4 in 1").mean
t4_2 = sp.get_tally(name="total from 4 in 2").mean
t4_3 = sp.get_tally(name="total from 4 in 3").mean
t4_4 = sp.get_tally(name="total from 4 in 4").mean
tglobal = sp.get_tally(name="total").mean
# From 1 and 2 is equivalent to from 3
assert_allclose(t1_1 + t2_1, t3_1, rtol=RTOL, atol=ATOL)
assert_allclose(t1_2 + t2_2, t3_2, rtol=RTOL, atol=ATOL)
assert_allclose(t1_3 + t2_3, t3_3, rtol=RTOL, atol=ATOL)
assert_allclose(t1_4 + t2_4, t3_4, rtol=RTOL, atol=ATOL)
# In 1 and 2 equivalent to in 3
assert_allclose(t1_1 + t1_2, t1_3, rtol=RTOL, atol=ATOL)
assert_allclose(t2_1 + t2_2, t2_3, rtol=RTOL, atol=ATOL)
assert_allclose(t3_1 + t3_2, t3_3, rtol=RTOL, atol=ATOL)
assert_allclose(t4_1 + t4_2, t4_3, rtol=RTOL, atol=ATOL)
# Comparison to global from 3
assert_allclose(t3_3 + t3_4 + t4_3 + t4_4, tglobal, rtol=RTOL, atol=ATOL)
# Comparison to global from 1 and 2
t_from_1_wo_3 = t1_1 + t1_2 + t1_4
t_from_2_wo_3 = t2_1 + t2_2 + t2_4
t_from_4_wo_3 = t4_1 + t4_2 + t4_4
assert_allclose(
t_from_1_wo_3 + t_from_2_wo_3 + t_from_4_wo_3,
tglobal,
rtol=RTOL,
atol=ATOL,
)
# 1 cannot contribute to 4 and 4 cannot contribute to 1 by symmetry
assert_equal(t1_4, np.zeros_like(t1_4))
assert_equal(t4_1, np.zeros_like(t4_1))
return super()._compare_results()
def test_filter_cellfrom(model):
harness = CellFromFilterTest("statepoint.15.h5", model)
harness.main()

View file

@ -118,15 +118,13 @@ class SurfaceSourceTestHarness(PyAPITestHarness):
@pytest.mark.surf_source_op('write')
def test_surface_source_write(model):
def test_surface_source_write(model, monkeypatch):
# Test result is based on 1 MPI process
np = config['mpi_np']
config['mpi_np'] = '1'
monkeypatch.setitem(config, "mpi_np", "1")
harness = SurfaceSourceTestHarness('statepoint.10.h5',
model,
'inputs_true_write.dat')
harness.main()
config['mpi_np'] = np
@pytest.mark.surf_source_op('read')

View file

@ -0,0 +1,66 @@
"""Helper script to visualize the surface_source.h5 files created with this test.
"""
import h5py
import matplotlib.pyplot as plt
if __name__ == "__main__":
# Select an option
# "show": 3D visualization using matplotlib
# "savefig": 2D representation using matplotlib and storing the fig under plot_2d.png
option = "show"
# option = "savefig"
# Select the case from its folder name
folder = "case-20"
# Reading the surface source file
with h5py.File(f"{folder}/surface_source_true.h5", "r") as fp:
source_bank = fp["source_bank"][()]
r_xs = source_bank['r']['x']
r_ys = source_bank['r']['y']
r_zs = source_bank['r']['z']
print("Size of the source bank: ", len(source_bank))
# Select data range to visualize
idx_1 = 0
idx_2 = -1
# Show 3D representation
if option == "show":
fig = plt.figure(figsize=(10, 10))
ax1 = fig.add_subplot(projection="3d", proj_type="ortho")
ax1.scatter(r_xs[idx_1:idx_2], r_ys[idx_1:idx_2], r_zs[idx_1:idx_2], marker=".")
ax1.view_init(0, 0)
ax1.xaxis.set_ticklabels([])
ax1.set_ylabel("y-axis [cm]")
ax1.set_zlabel("z-axis [cm]")
ax1.set_aspect("equal", "box")
plt.show()
# Save 2D representations
elif option == "savefig":
fig = plt.figure(figsize=(14, 5))
ax1 = fig.add_subplot(121, projection="3d", proj_type="ortho")
ax1.scatter(r_xs[idx_1:idx_2], r_ys[idx_1:idx_2], r_zs[idx_1:idx_2], marker=".")
ax1.view_init(0, 0)
ax1.xaxis.set_ticklabels([])
ax1.set_ylabel("y-axis [cm]")
ax1.set_zlabel("z-axis [cm]")
ax1.set_aspect("equal", "box")
ax2 = fig.add_subplot(122, projection="3d", proj_type="ortho")
ax2.scatter(r_xs[idx_1:idx_2], r_ys[idx_1:idx_2], r_zs[idx_1:idx_2], marker=".")
ax2.view_init(90, -90)
ax2.zaxis.set_ticklabels([])
ax2.set_xlabel("x-axis [cm]")
ax2.set_ylabel("y-axis [cm]")
ax2.set_aspect("equal", "box")
plt.savefig("plot_2d.png")

View file

@ -0,0 +1,54 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="11.0"/>
<nuclide ao="0.0004524" name="U234"/>
<nuclide ao="0.0506068" name="U235"/>
<nuclide ao="0.948709" name="U238"/>
<nuclide ao="0.0002318" name="U236"/>
<nuclide ao="2.0" name="O16"/>
</material>
<material id="2">
<density units="g/cm3" value="1.0"/>
<nuclide ao="2.0" name="H1"/>
<nuclide ao="1.0" name="O16"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3" universe="1"/>
<cell id="2" material="2" region="1 | -2 | 3" universe="1"/>
<cell fill="1" id="3" region="-5 4 -7 6 -9 8" universe="2"/>
<cell id="4" material="2" region="-11 10 -13 12 -15 14 (5 | -4 | 7 | -6 | 9 | -8)" universe="2"/>
<surface coeffs="0.0 0.0 2.0" id="1" type="z-cylinder"/>
<surface coeffs="-2.0" id="2" type="z-plane"/>
<surface coeffs="2.0" id="3" type="z-plane"/>
<surface coeffs="-3.0" id="4" type="x-plane"/>
<surface coeffs="3.0" id="5" type="x-plane"/>
<surface coeffs="-3.0" id="6" type="y-plane"/>
<surface coeffs="3.0" id="7" type="y-plane"/>
<surface coeffs="-3.0" id="8" type="z-plane"/>
<surface coeffs="3.0" id="9" type="z-plane"/>
<surface boundary="vacuum" coeffs="-4.0" id="10" type="x-plane"/>
<surface boundary="vacuum" coeffs="4.0" id="11" type="x-plane"/>
<surface boundary="vacuum" coeffs="-4.0" id="12" type="y-plane"/>
<surface boundary="vacuum" coeffs="4.0" id="13" type="y-plane"/>
<surface boundary="vacuum" coeffs="-4.0" id="14" type="z-plane"/>
<surface boundary="vacuum" coeffs="4.0" id="15" type="z-plane"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>1</inactive>
<source particle="neutron" strength="1.0" type="independent">
<space type="fission">
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
</space>
</source>
<surf_source_write>
<max_particles>300</max_particles>
</surf_source_write>
<seed>1</seed>
</settings>
</model>

View file

@ -0,0 +1,2 @@
k-combined:
5.169123E-02 9.144814E-03

View file

@ -0,0 +1,55 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="11.0"/>
<nuclide ao="0.0004524" name="U234"/>
<nuclide ao="0.0506068" name="U235"/>
<nuclide ao="0.948709" name="U238"/>
<nuclide ao="0.0002318" name="U236"/>
<nuclide ao="2.0" name="O16"/>
</material>
<material id="2">
<density units="g/cm3" value="1.0"/>
<nuclide ao="2.0" name="H1"/>
<nuclide ao="1.0" name="O16"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3" universe="1"/>
<cell id="2" material="2" region="1 | -2 | 3" universe="1"/>
<cell fill="1" id="3" region="-5 4 -7 6 -9 8" universe="2"/>
<cell id="4" material="2" region="-11 10 -13 12 -15 14 (5 | -4 | 7 | -6 | 9 | -8)" universe="2"/>
<surface coeffs="0.0 0.0 2.0" id="1" type="z-cylinder"/>
<surface coeffs="-2.0" id="2" type="z-plane"/>
<surface coeffs="2.0" id="3" type="z-plane"/>
<surface coeffs="-3.0" id="4" type="x-plane"/>
<surface coeffs="3.0" id="5" type="x-plane"/>
<surface coeffs="-3.0" id="6" type="y-plane"/>
<surface coeffs="3.0" id="7" type="y-plane"/>
<surface coeffs="-3.0" id="8" type="z-plane"/>
<surface coeffs="3.0" id="9" type="z-plane"/>
<surface boundary="vacuum" coeffs="-4.0" id="10" type="x-plane"/>
<surface boundary="vacuum" coeffs="4.0" id="11" type="x-plane"/>
<surface boundary="vacuum" coeffs="-4.0" id="12" type="y-plane"/>
<surface boundary="vacuum" coeffs="4.0" id="13" type="y-plane"/>
<surface boundary="vacuum" coeffs="-4.0" id="14" type="z-plane"/>
<surface boundary="vacuum" coeffs="4.0" id="15" type="z-plane"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>1</inactive>
<source particle="neutron" strength="1.0" type="independent">
<space type="fission">
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
</space>
</source>
<surf_source_write>
<surface_ids>8</surface_ids>
<max_particles>300</max_particles>
</surf_source_write>
<seed>1</seed>
</settings>
</model>

View file

@ -0,0 +1,2 @@
k-combined:
5.169123E-02 9.144814E-03

View file

@ -0,0 +1,55 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="11.0"/>
<nuclide ao="0.0004524" name="U234"/>
<nuclide ao="0.0506068" name="U235"/>
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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
<model>
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<seed>1</seed>
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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
<model>
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<cell id="1" material="1" region="-1 2 -3" universe="1"/>
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<seed>1</seed>
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</model>

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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
<model>
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<seed>1</seed>
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</model>

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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
<model>
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</model>

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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
<model>
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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
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k-combined:
5.169123E-02 9.144814E-03

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<?xml version='1.0' encoding='utf-8'?>
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k-combined:
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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
4.752377E-02 6.773395E-03

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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
4.752377E-02 6.773395E-03

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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
4.752377E-02 6.773395E-03

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@ -0,0 +1,48 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
1.496403E+00 3.891283E-02

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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
1.496403E+00 3.891283E-02

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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
1.496403E+00 3.891283E-02

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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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View file

@ -0,0 +1,2 @@
k-combined:
1.496403E+00 3.891283E-02

View file

@ -0,0 +1,48 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -0,0 +1,2 @@
k-combined:
1.149925E+00 2.542255E-01

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@ -0,0 +1,49 @@
<?xml version='1.0' encoding='utf-8'?>
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View file

@ -0,0 +1,2 @@
k-combined:
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View file

@ -0,0 +1,2 @@
k-combined:
5.169123E-02 9.144814E-03

View file

@ -0,0 +1,33 @@
<?xml version='1.0' encoding='utf-8'?>
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View file

@ -0,0 +1,2 @@
k-combined:
9.263843E-01 3.193920E-02

View file

@ -0,0 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
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View file

@ -0,0 +1,2 @@
k-combined:
9.263843E-01 3.193920E-02

View file

@ -0,0 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
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View file

@ -0,0 +1,2 @@
k-combined:
9.263843E-01 3.193920E-02

View file

@ -0,0 +1,35 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
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View file

@ -0,0 +1,2 @@
k-combined:
9.263843E-01 3.193920E-02

View file

@ -0,0 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
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View file

@ -0,0 +1,2 @@
k-combined:
9.263843E-01 3.193920E-02

View file

@ -0,0 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
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View file

@ -0,0 +1,2 @@
k-combined:
9.263843E-01 3.193920E-02

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