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Merge remote-tracking branch 'upstream/develop' into pyapi_filters

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Sterling Harper 2016-09-20 15:34:49 -04:00
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2
.travis.yml
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@ -42,7 +42,7 @@ install: true
before_script:
- if [[ ! -e $HOME/nndc_hdf5/cross_sections.xml ]]; then
wget https://anl.box.com/shared/static/68b2yhu8e6mx1f6hnbzz9mxsgg42d9ls.xz -O - | tar -C $HOME -xvJ;
wget https://anl.box.com/shared/static/fouwc8lh9he2wc97kzq65u4rp8zt9sgq.xz -O - | tar -C $HOME -xvJ;
fi
- export OPENMC_CROSS_SECTIONS=$HOME/nndc_hdf5/cross_sections.xml

36
docs/source/methods/cross_sections.rst
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@ -66,6 +66,8 @@ Other Methods
A good survey of other energy grid techniques, including unionized energy grids,
can be found in a paper by Leppanen_.
.. _windowed_multipole:
Windowed Multipole Representation
---------------------------------
@ -141,6 +143,40 @@ but not always the case. Future library versions may eliminate this issue.
The data format used by OpenMC to represent windowed multipole data is specified
in :ref:`io_data_wmp`.
.. _temperature_treatment:
Temperature Treatment
---------------------
At the beginning of a simulation, OpenMC collects a list of all temperatures
that are present in a model. It then uses this list to determine what cross
sections to load. The data that is loaded depends on what temperature method has
been selected. There are three methods available:
:Nearest: Cross sections are loaded only if they are within a specified
tolerance of the actual temperatures in the model.
:Interpolation: Cross sections are loaded at temperatures that bound the actual
temperatures in the model. During transport, cross sections for
each material are calculated using statistical linear-linear
interpolation between bounding temperature. Suppose cross
sections are available at temperatures :math:`T_1, T_2, ...,
T_n` and a material is assigned a temperature :math:`T` where
:math:`T_i < T < T_{i+1}`. Statistical interpolation is applied
as follows: a uniformly-distributed random number of the unit
interval, :math:`\xi`, is sampled. If :math:`\xi < (T -
T_i)/(T_{i+1} - T_i)`, then cross sections at temperature
:math:`T_{i+1}` are used. Otherwise, cross sections at
:math:`T_i` are used. This procedure is applied for pointwise
cross sections in the resolved resonance range, unresolved
resonance probability tables, and :math:`S(\alpha,\beta)`
thermal scattering tables.
:Multipole: Resolved resonance cross sections are calculated on-the-fly using
techniques/data described in :ref:`windowed_multipole`. Cross
section data is loaded for a single temperature and is used in the
unresolved resonance and fast energy ranges.
----------------
Multi-Group Data
----------------

83
docs/source/methods/geometry.rst
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@ -265,6 +265,8 @@ Again, we need to check whether the denominator is zero. If so, this means that
the particle's direction of flight is parallel to the plane and it will
therefore never hit the plane.
.. _cylinder_distance:
Cylinder Parallel to an Axis
----------------------------
@ -366,7 +368,74 @@ will then be either both positive or both negative. If they are both positive,
the smaller (closer) one will be the solution with a negative sign on the square
root of the discriminant.
.. TODO: Need to add derivation for x-cone, y-cone, and z-cone.
Cone Parallel to an Axis
------------------------
The equation for a cone parallel to, for example, the x-axis is :math:`(y -
y_0)^2 + (z - z_0)^2 = R^2(x - x_0)^2`. Thus, we need to solve :math:`(y + dv -
y_0)^2 + (z + dw - z_0)^2 = R^2(x + du - x_0)^2`. Let us define :math:`\bar{x} =
x - x_0`, :math:`\bar{y} = y - y_0`, and :math:`\bar{z} = z - z_0`. We then have
.. math::
:label: dist-xcone-1
(\bar{y} + dv)^2 + (\bar{z} + dw)^2 = R^2(\bar{x} + du)^2
Expanding equation :eq:`dist-xcone-1` and rearranging terms, we obtain
.. math::
:label: dist-xcylinder-2
(v^2 + w^2 - R^2u^2) d^2 + 2 (\bar{y}v + \bar{z}w - R^2\bar{x}u) d +
(\bar{y}^2 + \bar{z}^2 - R^2\bar{x}^2) = 0
Defining the terms
.. math::
:label: dist-quadric-terms
a = v^2 + w^2 - R^2u^2
k = \bar{y}v + \bar{z}w - R^2\bar{x}u
c = \bar{y}^2 + \bar{z}^2 - R^2\bar{x}^2
we then have the simple quadratic equation :math:`ad^2 + 2kd + c = 0` which can
be solved as described in :ref:`cylinder_distance`.
General Quadric
---------------
The equation for a general quadric surface is :math:`Ax^2 + By^2 + Cz^2 + Dxy +
Eyz + Fxz + Gx + Hy + Jz + K = 0`. Thus, we need to solve the equation
.. math::
:label: dist-quadric-1
A(x+du)^2 + B(y+dv)^2 + C(z+dw)^2 + D(x+du)(y+dv) + E(y+dv)(z+dw) + \\
F(x+du)(z+dw) + G(x+du) + H(y+dv) + J(z+dw) + K = 0
Expanding equation :eq:`dist-quadric-1` and rearranging terms, we obtain
.. math::
:label: dist-quadric-2
d^2(uv + vw + uw) + 2d(Aux + Bvy + Cwx + (D(uv + vx) + E(vz + wy) + \\
F(wx + uz))/2) + (x(Ax + Dy) + y(By + Ez) + z(Cz + Fx)) = 0
Defining the terms
.. math::
:label: dist-quadric-terms
a = uv + vw + uw
k = Aux + Bvy + Cwx + (D(uv + vx) + E(vz + wy) + F(wx + uz))/2
c = x(Ax + Dy) + y(By + Ez) + z(Cz + Fx)
we then have the simple quadratic equation :math:`ad^2 + 2kd + c = 0` which can
be solved as described in :ref:`cylinder_distance`.
.. _find-cell:
@ -810,6 +879,18 @@ form of the solution:
w' = w + \frac{2 (\bar{x}u + \bar{y}v - R^2\bar{z}w)}{R^2 (1 + R^2) \bar{z}}
General Quadric
---------------
A general quadric surface has the form :math:`f(x,y,z) = Ax^2 + By^2 + Cz^2 +
Dxy + Eyz + Fxz + Gx + Hy + Jz + K = 0`. Thus, the gradient to the surface is
.. math::
:label: reflection-quadric-grad
\nabla f = \left ( \begin{array}{c} 2Ax + Dy + Fz + G \\ 2By + Dx + Ez + H
\\ 2Cz + Ey + Fx + J \end{array} \right ).
.. _constructive solid geometry: http://en.wikipedia.org/wiki/Constructive_solid_geometry
.. _surfaces: http://en.wikipedia.org/wiki/Surface

81
docs/source/publications.rst
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@ -53,6 +53,16 @@ Benchmarking
Coupling and Multi-physics
--------------------------
- Matthew Ellis, Benoit Forget, Kord Smith, and Derek Gaston, "Continuous
Temperature Representation in Coupled OpenMC/MOOSE Simulations," *Proc. PHYSOR
2016*, Sun Valley, Idaho, May 1-5, 2016.
- Antonios G. Mylonakis, Melpomeni Varvayanni, and Nicolas Catsaros,
"Investigating a Matrix-free, Newton-based, Neutron-Monte
Carlo/Thermal-Hydraulic Coupling Scheme", *Proc. Int. Conf. Nuclear Energy for
New Europe*, Portoroz, Slovenia, Sep .14-17
(2015). `<https://www.researchgate.net/publication/282001032>`_
- Matt Ellis, Benoit Forget, Kord Smith, and Derek Gaston, "Preliminary coupling
of the Monte Carlo code OpenMC and the Multiphysics Object-Oriented Simulation
Environment (MOOSE) for analyzing Doppler feedback in Monte Carlo
@ -80,8 +90,17 @@ Geometry
Miscellaneous
-------------
- Yunzhao Li, Qingming He, Liangzhi Cao, Hongchun Wu, and Tiejun Zu, "Resonance
Elastic Scattering and Interference Effects Treatments in Subgroup Method,"
*Nucl. Eng. Tech.*, **48**, 339-350
(2016). `<http://dx.doi.org/10.1016/j.net.2015.12.015>`_
- William Boyd, Sterling Harper, and Paul K. Romano, "Equipping OpenMC for the
big data era," Accepted, *PHYSOR 2016*, Sun Valley, Idaho, May 1-5, 2016.
big data era," *Proc. PHYSOR*, Sun Valley, Idaho, May 1-5, 2016.
- Michal Kostal, Vojtech Rypar, Jan Milcak, Vlastimil Juricek, Evzen Losa,
Benoit Forget, and Sterling Harper, *Ann. Nucl. Energy*, **87**, 601-611
(2016). `<http://dx.doi.org/10.1016/j.anucene.2015.10.010>`_
- Qicang Shen, William Boyd, Benoit Forget, and Kord Smith, "Tally precision
triggers for the OpenMC Monte Carlo code," *Trans. Am. Nucl. Soc.*, **112**,
@ -95,6 +114,11 @@ Miscellaneous
Multi-group Cross Section Generation
------------------------------------
- Zhaoyuan Liu, Kord Smith, and Benoit Forget, "A Cumulative Migration Method
for Computing Rigorous Transport Cross Sections and Diffusion Coefficients for
LWR Lattices with Monte Carlo," *Proc. PHYSOR*, Sun Valley, Idaho, May
1-5, 2016.
- Adam G. Nelson and William R. Martin, "Improved Monte Carlo tallying of
multi-group scattering moments using the NDPP code," *Trans. Am. Nucl. Soc.*,
**113**, 645-648 (2015)
@ -108,18 +132,43 @@ Multi-group Cross Section Generation
Computational Methods Applied to Nuclear Science and Engineering*, Sun Valley,
Idaho, May 5--9 (2013).
------------
Nuclear Data
------------
------------------
Doppler Broadening
------------------
- Colin Josey, Pablo Ducru, Benoit Forget, and Kord Smith, "Windowed multipole
for cross section Doppler broadening," *J. Comput. Phys.*, In Press
for cross section Doppler broadening," *J. Comput. Phys.*, **307**, 715-727
(2016). `<http://dx.doi.org/10.1016/jcp.2015.08.013>`_
- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown,
"On-the-fly Doppler Broadening of Unresolved Resonance Region Cross Sections
via Probability Band Interpolation," *Proc. PHYSOR*, Sun Valley, Idaho, May
1-5, 2016.
- Colin Josey, Benoit Forget, and Kord Smith, "Windowed multipole sensitivity to
target accuracy of the optimization procedure," *J. Nucl. Sci. Technol.*,
**52**, 987-992 (2015). `<http://dx.doi.org/10.1080/00223131.2015.1035353>`_
- Paul K. Romano and Timothy H. Trumbull, "Comparison of algorithms for Doppler
broadening pointwise tabulated cross sections," *Ann. Nucl. Energy*, **75**,
358--364 (2015). `<http://dx.doi.org/10.1016/j.anucene.2014.08.046>`_
- Tuomas Viitanen, Jaakko Leppanen, and Benoit Forget, "Target motion sampling
temperature treatment technique with track-length esimators in OpenMC --
Preliminary results," *Proc. PHYSOR*, Kyoto, Japan, Sep. 28--Oct. 3 (2014).
- Benoit Forget, Sheng Xu, and Kord Smith, "Direct Doppler broadening in Monte
Carlo simulations using the multipole representation," *Ann. Nucl. Energy*,
**64**, 78--85 (2014). `<http://dx.doi.org/10.1016/j.anucene.2013.09.043>`_
------------
Nuclear Data
------------
- Paul K. Romano and Sterling M. Harper, "Nuclear data processing capabilities
in OpenMC", *Proc. Nuclear Data*, Sep. 11-16, 2016.
- Jonathan A. Walsh, Paul K. Romano, Benoit Forget, and Kord S. Smith,
"Optimizations of the energy grid search algorithm in continuous-energy Monte
Carlo particle transport codes", *Comput. Phys. Commun.*, **196**, 134-142
@ -139,29 +188,17 @@ Nuclear Data
performance analysis for varying cross section parameter regimes,"
*Proc. Joint Int. Conf. M&C+SNA+MC*, Nashville, Tennessee, Apr. 19--23 (2015).
- Paul K. Romano and Timothy H. Trumbull, "Comparison of algorithms for Doppler
broadening pointwise tabulated cross sections," *Ann. Nucl. Energy*, **75**,
358--364 (2015). `<http://dx.doi.org/10.1016/j.anucene.2014.08.046>`_
- Tuomas Viitanen, Jaakko Leppanen, and Benoit Forget, "Target motion sampling
temperature treatment technique with track-length esimators in OpenMC --
Preliminary results," *Proc. PHYSOR*, Kyoto, Japan, Sep. 28--Oct. 3 (2014).
- Jonathan A. Walsh, Benoit Forget, and Kord S. Smith, "Accelerated sampling
of the free gas resonance elastic scattering kernel," *Ann. Nucl. Energy*,
**69**, 116--124 (2014). `<http://dx.doi.org/10.1016/j.anucene.2014.01.017>`_
- Benoit Forget, Sheng Xu, and Kord Smith, "Direct Doppler broadening in Monte
Carlo simulations using the multipole representation," *Ann. Nucl. Energy*,
**64**, 78--85 (2014). `<http://dx.doi.org/10.1016/j.anucene.2013.09.043>`_
-----------
Parallelism
-----------
- Paul K. Romano, John R. Tramm, and Andrew R. Siegel, "Efficacy of hardware
threading for Monte Carlo particle transport calculations on multi- and
many-core systems," Accepted, *PHYSOR 2016*, Sun Valley, Idaho, May 1-5, 2016.
many-core systems," *PHYSOR 2016*, Sun Valley, Idaho, May 1-5, 2016.
- David Ozog, Allen D. Malony, and Andrew R. Siegel, "A performance analysis of
SIMD algorithms for Monte Carlo simulations of nuclear reactor cores,"
@ -228,3 +265,11 @@ Parallelism
- Paul K. Romano and Benoit Forget, "Parallel Fission Bank Algorithms in Monte
Carlo Criticality Calculations," *Nucl. Sci. Eng.*, **170**, 125--135
(2012). `<http://hdl.handle.net/1721.1/73569>`_
---------
Depletion
---------
- Kai Huang, Hongchun Wu, Yunzhao Li, and Liangzhi Cao, "Generalized depletion
chain simplification based of significance analysis," *Proc. PHYSOR*, Sun
Valley, Idaho, May 1-5, 2016.

552
docs/source/pythonapi/examples/mdgxs-part-i.ipynb
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1
docs/source/pythonapi/index.rst
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@ -298,6 +298,7 @@ Multi-delayed-group Cross Sections
openmc.mgxs.ChiDelayed
openmc.mgxs.DelayedNuFissionXS
openmc.mgxs.Beta
openmc.mgxs.DecayRate
Multi-group Cross Section Libraries
-----------------------------------

22
docs/source/usersguide/input.rst
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@ -725,13 +725,16 @@ a material default temperature.
``<temperature_method>`` Element
--------------------------------
The ``<temperature_method>`` element has an accepted value of "nearest" or
"interpolation". A value of "nearest" indicates that for each cell, the nearest
temperature at which cross sections are given is to be applied, within a given
tolerance (see :ref:`temperature_tolerance`). A value of "multipole" indicates
that the windowed multipole method should be used to evaluate
temperature-dependent cross sections in the resolved resonance range (a
:ref:`windowed multipole library <multipole_library>` must also be available).
The ``<temperature_method>`` element has an accepted value of "nearest",
"interpolation", or "multipole". A value of "nearest" indicates that for each
cell, the nearest temperature at which cross sections are given is to be
applied, within a given tolerance (see :ref:`temperature_tolerance`). A value of
"interpolation" indicates that cross sections are to be linear-linear
interpolated between temperatures at which nuclear data are present (see
:ref:`temperature_treatment`). A value of "multipole" indicates that the
windowed multipole method should be used to evaluate temperature-dependent cross
sections in the resolved resonance range (a :ref:`windowed multipole library
<multipole_library>` must also be available).
*Default*: "nearest"
@ -1887,6 +1890,11 @@ The ``<tally>`` element accepts the following sub-elements:
| |deposited locally. Units are MeV per source |
| |paticle. |
+----------------------+---------------------------------------------------+
|decay-rate |The delayed-nu-fission-weighted decay rate where |
| |the decay rate is in units of inverse seconds. |
| |This score type is not used in the |
| |multi-group :ref:`energy_mode`. |
+----------------------+---------------------------------------------------+
.. note::
The ``analog`` estimator is actually identical to the ``collision``

20
examples/xml/pincell_multigroup/mg_cross_sections.xml
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@ -40,9 +40,9 @@
<!-- units of MeV/cm -->
<!-- If no kappa fission tallies, this is not needed; it will not be loaded
if there is no kappa fission scores anyways -->
<k_fission>
<kappa_fission>
1.0 1.0 1.0 1.0 1.0 1.0 1.0
</k_fission>
</kappa_fission>
<!-- for consistency must include nu-scatter -->
<!-- will be a matrix of (order+1) x g_in x g_out -->
@ -100,9 +100,9 @@
</fission>
<!-- units of MeV/cm -->
<k_fission>
<kappa_fission>
1.0 1.0 1.0 1.0 1.0 1.0 1.0
</k_fission>
</kappa_fission>
<!-- for consistency must include nu-scatter -->
<!-- will be a matrix of (order+1) x g_in x g_out -->
@ -156,9 +156,9 @@
</fission>
<!-- units of MeV/cm -->
<k_fission>
<kappa_fission>
1.0 1.0 1.0 1.0 1.0 1.0 1.0
</k_fission>
</kappa_fission>
<!-- for consistency must include nu-scatter -->
<!-- will be a matrix of (order+1) x g_in x g_out -->
@ -212,9 +212,9 @@
</fission>
<!-- units of MeV/cm -->
<k_fission>
<kappa_fission>
1.0 1.0 1.0 1.0 1.0 1.0 1.0
</k_fission>
</kappa_fission>
<!-- for consistency must include nu-scatter -->
<!-- will be a matrix of (order+1) x g_in x g_out -->
@ -262,9 +262,9 @@
</fission>
<!-- units of MeV/cm -->
<k_fission>
<kappa_fission>
1.0 1.0 1.0 1.0 1.0 1.0 1.0
</k_fission>
</kappa_fission>
<!-- for consistency must include nu-scatter -->
<!-- will be a matrix of (order+1) x g_in x g_out -->

2
openmc/data/neutron.py
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@ -478,7 +478,7 @@ class IncidentNeutron(EqualityMixin):
if len(rxs) > 0:
data.summed_reactions[mt_sum] = rx = Reaction(mt_sum)
for T in data.temperatures:
rx.xs[T] = Sum([rx.xs[T] for rx in rxs])
rx.xs[T] = Sum([rx_i.xs[T] for rx_i in rxs])
# Read unresolved resonance probability tables
if 'urr' in group:

4
openmc/data/reaction.py
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@ -107,7 +107,9 @@ def _get_fission_products(ace):
for group in range(n_group):
delayed_neutron = Product('neutron')
delayed_neutron.emission_mode = 'delayed'
delayed_neutron.decay_rate = ace.xss[idx]
# Convert units of inverse shakes to inverse seconds
delayed_neutron.decay_rate = ace.xss[idx] * 1.e8
group_probability = Tabulated1D.from_ace(ace, idx + 1)
if np.all(group_probability.y == group_probability.y[0]):

12
openmc/filter.py
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@ -20,12 +20,12 @@ _FILTER_TYPES = ['universe', 'material', 'cell', 'cellborn', 'surface',
'mesh', 'energy', 'energyout', 'mu', 'polar', 'azimuthal',
'distribcell', 'delayedgroup']
_CURRENT_NAMES = {1: 'x-min out', 2: 'x-max out',
3: 'y-min out', 4: 'y-max out',
5: 'z-min out', 6: 'z-max out',
7: 'x-min in', 8: 'x-max in',
9: 'y-min in', 10: 'y-max in',
11: 'z-min in', 12: 'z-max in'}
_CURRENT_NAMES = {1: 'x-min out', 2: 'x-min in',
3: 'x-max out', 4: 'x-max in',
5: 'y-min out', 6: 'y-min in',
7: 'y-max out', 8: 'y-max in',
9: 'z-min out', 10: 'z-min in',
11: 'z-max out', 12: 'z-max in'}
class FilterMeta(ABCMeta):

5
openmc/geometry.py
View file

@ -64,7 +64,7 @@ class Geometry(object):
if cell.id in volume_calc.results:
cell.add_volume_information(volume_calc)
def export_to_xml(self):
def export_to_xml(self, path='geometry.xml'):
"""Create a geometry.xml file that can be used for a simulation.
"""
@ -82,8 +82,7 @@ class Geometry(object):
# Write the XML Tree to the geometry.xml file
tree = ET.ElementTree(geometry_file)
tree.write("geometry.xml", xml_declaration=True, encoding='utf-8',
method="xml")
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")
def find(self, point):
"""Find cells/universes/lattices which contain a given point

31
openmc/material.py
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@ -41,19 +41,16 @@ class Material(object):
name : str, optional
Name of the material. If not specified, the name will be the empty
string.
temperature : str, optional
The temperature identifier applied to this material. The units are
in Kelvin and the temperature rounded to the nearest integer.
For example, a tempreature of 293.6K would be provided as '294K'
temperature : float, optional
Temperature of the material in Kelvin. If not specified, the material
inherits the default temperature applied to the model.
Attributes
----------
id : int
Unique identifier for the material
temperature : str
The temperature identifier applied to this material. The units are
in Kelvin and the temperature rounded to the nearest integer.
For example, a tempreature of 293.6K would be provided as '294K'
temperature : float
Temperature of the material in Kelvin.
density : float
Density of the material (units defined separately)
density_units : str
@ -217,12 +214,9 @@ class Material(object):
@temperature.setter
def temperature(self, temperature):
if temperature is not None:
cv.check_type('Temperature for Material ID="{0}"'.format(self._id),
temperature, basestring)
self._temperature = temperature
else:
self._temperature = ''
cv.check_type('Temperature for Material ID="{0}"'.format(self._id),
temperature, (Real, type(None)))
self._temperature = temperature
def set_density(self, units, density=None):
"""Set the density of the material
@ -631,9 +625,9 @@ class Material(object):
element.set("name", str(self._name))
# Create temperature XML subelement
if len(self.temperature) > 0:
if self.temperature is not None:
subelement = ET.SubElement(element, "temperature")
subelement.text = self.temperature
subelement.text = str(self.temperature)
# Create density XML subelement
subelement = ET.SubElement(element, "density")
@ -817,7 +811,7 @@ class Materials(cv.CheckedList):
xml_element = material.get_material_xml()
self._materials_file.append(xml_element)
def export_to_xml(self):
def export_to_xml(self, path='materials.xml'):
"""Create a materials.xml file that can be used for a simulation.
"""
@ -833,5 +827,4 @@ class Materials(cv.CheckedList):
# Write the XML Tree to the materials.xml file
tree = ET.ElementTree(self._materials_file)
tree.write("materials.xml", xml_declaration=True,
encoding='utf-8', method="xml")
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")

50
openmc/mesh.py
View file

@ -23,7 +23,7 @@ def reset_auto_mesh_id():
class Mesh(object):
"""A structured Cartesian mesh in two or three dimensions
"""A structured Cartesian mesh in one, two, or three dimensions
Parameters
----------
@ -147,25 +147,25 @@ class Mesh(object):
@dimension.setter
def dimension(self, dimension):
cv.check_type('mesh dimension', dimension, Iterable, Integral)
cv.check_length('mesh dimension', dimension, 2, 3)
cv.check_length('mesh dimension', dimension, 1, 3)
self._dimension = dimension
@lower_left.setter
def lower_left(self, lower_left):
cv.check_type('mesh lower_left', lower_left, Iterable, Real)
cv.check_length('mesh lower_left', lower_left, 2, 3)
cv.check_length('mesh lower_left', lower_left, 1, 3)
self._lower_left = lower_left
@upper_right.setter
def upper_right(self, upper_right):
cv.check_type('mesh upper_right', upper_right, Iterable, Real)
cv.check_length('mesh upper_right', upper_right, 2, 3)
cv.check_length('mesh upper_right', upper_right, 1, 3)
self._upper_right = upper_right
@width.setter
def width(self, width):
cv.check_type('mesh width', width, Iterable, Real)
cv.check_length('mesh width', width, 2, 3)
cv.check_length('mesh width', width, 1, 3)
self._width = width
def __hash__(self):
@ -204,7 +204,10 @@ class Mesh(object):
"""
if len(self.dimension) == 2:
if len(self.dimension) == 1:
for x in range(self.dimension[0]):
yield [x + 1, 1, 1]
elif len(self.dimension) == 2:
for x in range(self.dimension[0]):
for y in range(self.dimension[1]):
yield [x + 1, y + 1, 1]
@ -272,7 +275,6 @@ class Mesh(object):
"""
twod = len(self.dimension) == 2
cv.check_length('bc', bc, length_min=4, length_max=6)
for entry in bc:
cv.check_value('bc', entry, ['transmission', 'vacuum',
@ -283,11 +285,18 @@ class Mesh(object):
boundary_type=bc[0]),
openmc.XPlane(x0=self.upper_right[0],
boundary_type=bc[1])]
yplanes = [openmc.YPlane(y0=self.lower_left[1],
boundary_type=bc[2]),
openmc.YPlane(y0=self.upper_right[1],
boundary_type=bc[3])]
if twod:
if len(self.dimension) == 1:
yplanes = [openmc.YPlane(y0=np.finfo(np.float).min,
boundary_type='reflective'),
openmc.YPlane(y0=np.finfo(np.float).max,
boundary_type='reflective')]
else:
yplanes = [openmc.YPlane(y0=self.lower_left[1],
boundary_type=bc[2]),
openmc.YPlane(y0=self.upper_right[1],
boundary_type=bc[3])]
if len(self.dimension) <= 2:
zplanes = [openmc.ZPlane(z0=np.finfo(np.float).min,
boundary_type='reflective'),
openmc.ZPlane(z0=np.finfo(np.float).max,
@ -308,7 +317,11 @@ class Mesh(object):
universes = np.ndarray(self.dimension[::-1], dtype=np.object)
cells = []
for [i, j, k] in self.cell_generator():
if twod:
if len(self.dimension) == 1:
universes[i - 1] = openmc.Universe()
cells.append(openmc.Cell())
universes[i - 1].add_cells([cells[-1]])
elif len(self.dimension) == 2:
universes[j - 1, i - 1] = openmc.Universe()
cells.append(openmc.Cell())
universes[j - 1, i - 1].add_cells([cells[-1]])
@ -325,11 +338,16 @@ class Mesh(object):
else:
dx = ((self.upper_right[0] - self.lower_left[0]) /
self.dimension[0])
dy = ((self.upper_right[1] - self.lower_left[1]) /
self.dimension[1])
if twod:
if len(self.dimension) == 1:
lattice.pitch = [dx]
elif len(self.dimension) == 2:
dy = ((self.upper_right[1] - self.lower_left[1]) /
self.dimension[1])
lattice.pitch = [dx, dy]
else:
dy = ((self.upper_right[1] - self.lower_left[1]) /
self.dimension[1])
dz = ((self.upper_right[2] - self.lower_left[2]) /
self.dimension[2])
lattice.pitch = [dx, dy, dz]

159
openmc/mgxs/mdgxs.py
View file

@ -21,7 +21,8 @@ if sys.version_info[0] >= 3:
# Supported cross section types
MDGXS_TYPES = ['delayed-nu-fission',
'chi-delayed',
'beta']
'beta',
'decay-rate']
# Maximum number of delayed groups, from src/constants.F90
MAX_DELAYED_GROUPS = 8
@ -214,7 +215,7 @@ class MDGXS(MGXS):
Parameters
----------
mdgxs_type : {'delayed-nu-fission', 'chi-delayed', 'beta'}
mdgxs_type : {'delayed-nu-fission', 'chi-delayed', 'beta', 'decay-rate'}
The type of multi-delayed-group cross section object to return
domain : openmc.Material or openmc.Cell or openmc.Universe or
openmc.Mesh
@ -250,6 +251,8 @@ class MDGXS(MGXS):
delayed_groups)
elif mdgxs_type == 'beta':
mdgxs = Beta(domain, domain_type, energy_groups, delayed_groups)
elif mdgxs_type == 'decay-rate':
mdgxs = DecayRate(domain, domain_type, energy_groups, delayed_groups)
mdgxs.by_nuclide = by_nuclide
mdgxs.name = name
@ -1577,3 +1580,155 @@ class Beta(MDGXS):
super(Beta, self)._compute_xs()
return self._xs_tally
class DecayRate(MDGXS):
r"""The decay rate for delayed neutron precursors.
This class can be used for both OpenMC input generation and tally data
post-processing to compute spatially-homogenized and energy-integrated
multi-group and multi-delayed group cross sections for multi-group
neutronics calculations. At a minimum, one needs to set the
:attr:`DecayRate.energy_groups` and :attr:`DecayRate.domain` properties.
Tallies for the flux and appropriate reaction rates over the specified
domain are generated automatically via the :attr:`DecayRate.tallies`
property, which can then be appended to a :class:`openmc.Tallies` instance.
For post-processing, the :meth:`MGXS.load_from_statepoint` will pull in the
necessary data to compute multi-group cross sections from a
:class:`openmc.StatePoint` instance. The derived multi-group cross section
can then be obtained from the :attr:`DecayRate.xs_tally` property.
For a spatial domain :math:`V`, energy group :math:`[E_g,E_{g-1}]`, and
delayed group :math:`d`, the decay rate is calculated as:
.. math::
\langle \lambda_d \nu^d \sigma_f \phi \rangle &= \int_{r \in V} dr
\int_{4\pi} d\Omega' \int_0^\infty dE' \int_0^\infty dE \; \lambda_d \nu^d
\sigma_f (r, E') \psi(r, E', \Omega') \\
\langle \nu^d \sigma_f \phi \rangle &= \int_{r \in V} dr \int_{4\pi}
d\Omega' \int_0^\infty dE' \int_0^\infty dE \; \chi(E) \nu^d
\sigma_f (r, E') \psi(r, E', \Omega') \\
\lambda_d &= \frac{\langle \lambda_d \nu^d \sigma_f \phi \rangle}
{\langle \nu^d \sigma_f \phi \rangle}
Parameters
----------
domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.Mesh
The domain for spatial homogenization
domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'}
The domain type for spatial homogenization
groups : openmc.mgxs.EnergyGroups
The energy group structure for energy condensation
by_nuclide : bool
If true, computes cross sections for each nuclide in domain
name : str, optional
Name of the multi-group cross section. Used as a label to identify
tallies in OpenMC 'tallies.xml' file.
delayed_groups : list of int
Delayed groups to filter out the xs
Attributes
----------
name : str, optional
Name of the multi-group cross section
rxn_type : str
Reaction type (e.g., 'total', 'nu-fission', etc.)
by_nuclide : bool
If true, computes cross sections for each nuclide in domain
domain : Material or Cell or Universe or Mesh
Domain for spatial homogenization
domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'}
Domain type for spatial homogenization
energy_groups : openmc.mgxs.EnergyGroups
Energy group structure for energy condensation
delayed_groups : list of int
Delayed groups to filter out the xs
tally_trigger : openmc.Trigger
An (optional) tally precision trigger given to each tally used to
compute the cross section
scores : list of str
The scores in each tally used to compute the multi-group cross section
filters : list of openmc.Filter
The filters in each tally used to compute the multi-group cross section
tally_keys : list of str
The keys into the tallies dictionary for each tally used to compute
the multi-group cross section
estimator : {'tracklength', 'analog'}
The tally estimator used to compute the multi-group cross section
tallies : collections.OrderedDict
OpenMC tallies needed to compute the multi-group cross section. The keys
are strings listed in the :attr:`DecayRate.tally_keys` property and
values are instances of :class:`openmc.Tally`.
rxn_rate_tally : openmc.Tally
Derived tally for the reaction rate tally used in the numerator to
compute the multi-group cross section. This attribute is None
unless the multi-group cross section has been computed.
xs_tally : openmc.Tally
Derived tally for the multi-group cross section. This attribute
is None unless the multi-group cross section has been computed.
num_subdomains : int
The number of subdomains is unity for 'material', 'cell' and 'universe'
domain types. When the This is equal to the number of cell instances
for 'distribcell' domain types (it is equal to unity prior to loading
tally data from a statepoint file).
num_nuclides : int
The number of nuclides for which the multi-group cross section is
being tracked. This is unity if the by_nuclide attribute is False.
nuclides : Iterable of str or 'sum'
The optional user-specified nuclides for which to compute cross
sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides
are not specified by the user, all nuclides in the spatial domain
are included. This attribute is 'sum' if by_nuclide is false.
sparse : bool
Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format
for compressed data storage
loaded_sp : bool
Whether or not a statepoint file has been loaded with tally data
derived : bool
Whether or not the MGXS is merged from one or more other MGXS
hdf5_key : str
The key used to index multi-group cross sections in an HDF5 data store
"""
def __init__(self, domain=None, domain_type=None, energy_groups=None,
delayed_groups=None, by_nuclide=False, name=''):
super(DecayRate, self).__init__(domain, domain_type, energy_groups,
delayed_groups, by_nuclide, name)
self._rxn_type = 'decay-rate'
self._estimator = 'analog'
@property
def scores(self):
return ['delayed-nu-fission', 'decay-rate']
@property
def tally_keys(self):
return ['delayed-nu-fission', 'decay-rate']
@property
def filters(self):
# Create the non-domain specific Filters for the Tallies
group_edges = self.energy_groups.group_edges
energy_filter = openmc.Filter('energy', group_edges)
if self.delayed_groups != None:
delayed_filter = openmc.Filter('delayedgroup', self.delayed_groups)
return [[delayed_filter, energy_filter], [delayed_filter, energy_filter]]
else:
return [[energy_filter], [energy_filter]]
@property
def xs_tally(self):
if self._xs_tally is None:
delayed_nu_fission = self.tallies['delayed-nu-fission']
# Compute the decay rate
self._xs_tally = self.rxn_rate_tally / delayed_nu_fission
super(DecayRate, self)._compute_xs()
return self._xs_tally

5
openmc/plots.py
View file

@ -616,7 +616,7 @@ class Plots(cv.CheckedList):
self._plots_file.append(xml_element)
def export_to_xml(self):
def export_to_xml(self, path='plots.xml'):
"""Create a plots.xml file that can be used by OpenMC.
"""
@ -631,5 +631,4 @@ class Plots(cv.CheckedList):
# Write the XML Tree to the plots.xml file
tree = ET.ElementTree(self._plots_file)
tree.write("plots.xml", xml_declaration=True,
encoding='utf-8', method="xml")
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")

5
openmc/settings.py
View file

@ -1118,7 +1118,7 @@ class Settings(object):
for r in self.resonance_scattering:
elem.append(r.to_xml_element())
def export_to_xml(self):
def export_to_xml(self, path='settings.xml'):
"""Create a settings.xml file that can be used for a simulation.
"""
@ -1162,8 +1162,7 @@ class Settings(object):
# Write the XML Tree to the settings.xml file
tree = ET.ElementTree(self._settings_file)
tree.write("settings.xml", xml_declaration=True,
encoding='utf-8', method="xml")
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")
class ResonanceScattering(object):

25
src/constants.F90
View file

@ -296,7 +296,7 @@ module constants
EVENT_ABSORB = 2
! Tally score type
integer, parameter :: N_SCORE_TYPES = 23
integer, parameter :: N_SCORE_TYPES = 24
integer, parameter :: &
SCORE_FLUX = -1, & ! flux
SCORE_TOTAL = -2, & ! total reaction rate
@ -320,7 +320,8 @@ module constants
SCORE_PROMPT_NU_FISSION = -20, & ! prompt neutron production rate
SCORE_INVERSE_VELOCITY = -21, & ! flux-weighted inverse velocity
SCORE_FISS_Q_PROMPT = -22, & ! prompt fission Q-value
SCORE_FISS_Q_RECOV = -23 ! recoverable fission Q-value
SCORE_FISS_Q_RECOV = -23, & ! recoverable fission Q-value
SCORE_DECAY_RATE = -24 ! delayed neutron precursor decay rate
! Maximum scattering order supported
integer, parameter :: MAX_ANG_ORDER = 10
@ -366,16 +367,16 @@ module constants
! Tally surface current directions
integer, parameter :: &
OUT_LEFT = 1, & ! x min
OUT_RIGHT = 2, & ! x max
OUT_BACK = 3, & ! y min
OUT_FRONT = 4, & ! y max
OUT_BOTTOM = 5, & ! z min
OUT_TOP = 6, & ! z max
IN_LEFT = 7, & ! x min
IN_RIGHT = 8, & ! x max
IN_BACK = 9, & ! y min
IN_FRONT = 10, & ! y max
IN_BOTTOM = 11, & ! z min
IN_LEFT = 2, & ! x min
OUT_RIGHT = 3, & ! x max
IN_RIGHT = 4, & ! x max
OUT_BACK = 5, & ! y min
IN_BACK = 6, & ! y min
OUT_FRONT = 7, & ! y max
IN_FRONT = 8, & ! y max
OUT_BOTTOM = 9, & ! z min
IN_BOTTOM = 10, & ! z min
OUT_TOP = 11, & ! z max
IN_TOP = 12 ! z max
! Tally trigger types and threshold

51
src/cross_section.F90
View file

@ -162,15 +162,33 @@ contains
! temperature. Note that there is no tolerance here, so this
! temperature could be very far off!
kT = sqrtkT**2
i_temp = minloc(abs(nuclides(i_nuclide) % kTs - kT), dim=1)
end if
else
! If not using multipole data, do a linear search on temperature
kT = sqrtkT**2
do i_temp = 1, size(nuclides(i_nuclide) % kTs)
if (abs(nuclides(i_nuclide) % kTs(i_temp) - kT) < &
K_BOLTZMANN*temperature_tolerance) exit
end do
select case (temperature_method)
case (TEMPERATURE_NEAREST)
! If using nearest temperature, do linear search on temperature
do i_temp = 1, size(nuc % kTs)
if (abs(nuc % kTs(i_temp) - kT) < K_BOLTZMANN * &
temperature_tolerance) exit
end do
case (TEMPERATURE_INTERPOLATION)
! Find temperatures that bound the actual temperature
do i_temp = 1, size(nuc % kTs) - 1
if (nuc % kTs(i_temp) <= kT .and. kT < nuc % kTs(i_temp + 1)) exit
end do
! Randomly sample between temperature i and i+1
f = (kT - nuc % kTs(i_temp)) / &
(nuc % kTs(i_temp + 1) - nuc % kTs(i_temp))
if (f > prn()) i_temp = i_temp + 1
case (TEMPERATURE_MULTIPOLE)
i_temp = minloc(abs(nuclides(i_nuclide) % kTs - kT), dim=1)
end select
end if
! Evaluate multipole or interpolate
@ -317,10 +335,25 @@ contains
! Determine temperature for S(a,b) table
kT = sqrtkT**2
do i_temp = 1, size(sab_tables(i_sab) % kTs)
if (abs(sab_tables(i_sab) % kTs(i_temp) - kT) < &
K_BOLTZMANN*temperature_tolerance) exit
end do
if (temperature_method == TEMPERATURE_NEAREST) then
! If using nearest temperature, do linear search on temperature
do i_temp = 1, size(sab_tables(i_sab) % kTs)
if (abs(sab_tables(i_sab) % kTs(i_temp) - kT) < &
K_BOLTZMANN*temperature_tolerance) exit
end do
else
! Find temperatures that bound the actual temperature
do i_temp = 1, size(sab_tables(i_sab) % kTs) - 1
if (sab_tables(i_sab) % kTs(i_temp) <= kT .and. &
kT < sab_tables(i_sab) % kTs(i_temp + 1)) exit
end do
! Randomly sample between temperature i and i+1
f = (kT - sab_tables(i_sab) % kTs(i_temp)) / &
(sab_tables(i_sab) % kTs(i_temp + 1) - sab_tables(i_sab) % kTs(i_temp))
if (f > prn()) i_temp = i_temp + 1
end if
! Get pointer to S(a,b) table
associate (sab => sab_tables(i_sab) % data(i_temp))

2
src/endf.F90
View file

@ -40,6 +40,8 @@ contains
string = "fission"
case (SCORE_NU_FISSION)
string = "nu-fission"
case (SCORE_DECAY_RATE)
string = "decay-rate"
case (SCORE_DELAYED_NU_FISSION)
string = "delayed-nu-fission"
case (SCORE_PROMPT_NU_FISSION)

54
src/input_xml.F90
View file

@ -2716,8 +2716,8 @@ contains
! Determine number of dimensions for mesh
n = get_arraysize_integer(node_mesh, "dimension")
if (n /= 2 .and. n /= 3) then
call fatal_error("Mesh must be two or three dimensions.")
if (n /= 1 .and. n /= 2 .and. n /= 3) then
call fatal_error("Mesh must be one, two, or three dimensions.")
end if
m % n_dimension = n
@ -3230,22 +3230,6 @@ contains
! Check if total material was specified
if (trim(sarray(j)) == 'total') then
! Check if a delayedgroup filter is present for this tally
do l = 1, size(t % filters)
select type(filt => t % filters(l) % obj)
type is (DelayedGroupFilter)
call warning("A delayedgroup filter was used on a total &
&nuclide tally. Cross section libraries are not &
&guaranteed to have the same delayed group structure &
&across all isotopes. In particular, ENDF/B-VII.1 does &
&not have a consistent delayed group structure across &
&all isotopes while the JEFF 3.1.1 library has the same &
&delayed group structure across all isotopes. Use with &
&caution!")
end select
end do
t % nuclide_bins(j) = -1
cycle
end if
@ -3290,20 +3274,6 @@ contains
allocate(t % nuclide_bins(1))
t % nuclide_bins(1) = -1
t % n_nuclide_bins = 1
! Check if a delayedgroup filter is present for this tally
do l = 1, size(t % filters)
select type(filt => t % filters(l) % obj)
type is (DelayedGroupFilter)
call warning("A delayedgroup filter was used on a total nuclide &
&tally. Cross section libraries are not guaranteed to have the&
& same delayed group structure across all isotopes. In &
&particular, ENDF/B-VII.1 does not have a consistent delayed &
&group structure across all isotopes while the JEFF 3.1.1 &
&library has the same delayed group structure across all &
&isotopes. Use with caution!")
end select
end do
end if
! =======================================================================
@ -3417,8 +3387,9 @@ contains
end if
! Check if delayed group filter is used with any score besides
! delayed-nu-fission
if (score_name /= 'delayed-nu-fission' .and. &
! delayed-nu-fission or decay-rate
if ((score_name /= 'delayed-nu-fission' .and. &
score_name /= 'decay-rate') .and. &
t % find_filter(FILTER_DELAYEDGROUP) > 0) then
call fatal_error("Cannot tally " // trim(score_name) // " with a &
&delayedgroup filter.")
@ -3572,6 +3543,9 @@ contains
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
end if
case ('decay-rate')
t % score_bins(j) = SCORE_DECAY_RATE
t % estimator = ESTIMATOR_ANALOG
case ('delayed-nu-fission')
t % score_bins(j) = SCORE_DELAYED_NU_FISSION
if (t % find_filter(FILTER_ENERGYOUT) > 0) then
@ -3633,7 +3607,9 @@ contains
type is (SurfaceFilter)
filt % n_bins = 4 * m % n_dimension
allocate(filt % surfaces(4 * m % n_dimension))
if (m % n_dimension == 2) then
if (m % n_dimension == 1) then
filt % surfaces = (/ OUT_LEFT, OUT_RIGHT, IN_LEFT, IN_RIGHT /)
elseif (m % n_dimension == 2) then
filt % surfaces = (/ OUT_LEFT, OUT_RIGHT, OUT_BACK, OUT_FRONT, &
IN_LEFT, IN_RIGHT, IN_BACK, IN_FRONT /)
elseif (m % n_dimension == 3) then
@ -4948,7 +4924,7 @@ contains
call names % push_back('Ga0')
call densities % push_back(density)
else
call names % push_back('Ha69')
call names % push_back('Ga69')
call densities % push_back(density * 0.60108_8)
call names % push_back('Ga71')
call densities % push_back(density * 0.39892_8)
@ -5840,7 +5816,7 @@ contains
file_id = file_open(libraries(i_library) % path, 'r')
group_id = open_group(file_id, name)
call sab_tables(i_sab) % from_hdf5(group_id, sab_temps(i_sab), &
temperature_tolerance)
temperature_method, temperature_tolerance)
call close_group(group_id)
call file_close(file_id)
@ -5993,6 +5969,7 @@ contains
integer :: i, j
integer :: i_library
integer :: method
integer(HID_T) :: file_id
integer(HID_T) :: group_id
real(8) :: xs_cdf_sum
@ -6020,8 +5997,9 @@ contains
! Read nuclide data from HDF5
file_id = file_open(libraries(i_library) % path, 'r')
group_id = open_group(file_id, name)
method = TEMPERATURE_NEAREST
call resonant_nuc % from_hdf5(group_id, temperature, &
TEMPERATURE_NEAREST, 1000.0_8)
method, 1000.0_8)
call close_group(group_id)
call file_close(file_id)

114
src/mesh.F90
View file

@ -22,39 +22,29 @@ contains
real(8), intent(in) :: xyz(:) ! coordinates
integer, intent(out) :: bin ! tally bin
integer :: n ! size of mesh (2 or 3)
integer :: n ! size of mesh
integer :: d ! mesh dimension index
integer :: ijk(3) ! indices in mesh
logical :: in_mesh ! was given coordinate in mesh at all?
! Get number of dimensions
n = m % n_dimension
! Check for cases where particle is outside of mesh
if (xyz(1) < m % lower_left(1)) then
bin = NO_BIN_FOUND
return
elseif (xyz(1) > m % upper_right(1)) then
bin = NO_BIN_FOUND
return
elseif (xyz(2) < m % lower_left(2)) then
bin = NO_BIN_FOUND
return
elseif (xyz(2) > m % upper_right(2)) then
bin = NO_BIN_FOUND
return
end if
if (n > 2) then
if (xyz(3) < m % lower_left(3)) then
! Loop over the dimensions of the mesh
do d = 1, n
! Check for cases where particle is outside of mesh
if (xyz(d) < m % lower_left(d)) then
bin = NO_BIN_FOUND
return
elseif (xyz(3) > m % upper_right(3)) then
elseif (xyz(d) > m % upper_right(d)) then
bin = NO_BIN_FOUND
return
end if
end if
end do
! Determine indices
call get_mesh_indices(m, xyz(1:n), ijk(1:n), in_mesh)
call get_mesh_indices(m, xyz, ijk, in_mesh)
! Convert indices to bin
if (in_mesh) then
@ -76,7 +66,7 @@ contains
logical, intent(out) :: in_mesh ! were given coords in mesh?
! Find particle in mesh
ijk = ceiling((xyz(:m % n_dimension) - m % lower_left)/m % width)
ijk(:m % n_dimension) = ceiling((xyz(:m % n_dimension) - m % lower_left)/m % width)
! Determine if particle is in mesh
if (any(ijk(:m % n_dimension) < 1) .or. &
@ -89,8 +79,8 @@ contains
end subroutine get_mesh_indices
!===============================================================================
! MESH_INDICES_TO_BIN maps (i,j) or (i,j,k) indices to a single bin number for
! use in a TallyObject results array
! MESH_INDICES_TO_BIN maps (i), (i,j), or (i,j,k) indices to a single bin number
! for use in a TallyObject results array
!===============================================================================
pure function mesh_indices_to_bin(m, ijk) result(bin)
@ -98,23 +88,20 @@ contains
integer, intent(in) :: ijk(:)
integer :: bin
integer :: n_x ! number of mesh cells in x direction
integer :: n_y ! number of mesh cells in y direction
n_x = m % dimension(1)
n_y = m % dimension(2)
if (m % n_dimension == 2) then
bin = (ijk(2) - 1)*n_x + ijk(1)
if (m % n_dimension == 1) then
bin = ijk(1)
elseif (m % n_dimension == 2) then
bin = (ijk(2) - 1) * m % dimension(1) + ijk(1)
elseif (m % n_dimension == 3) then
bin = (ijk(3) - 1)*n_y*n_x + (ijk(2) - 1)*n_x + ijk(1)
bin = ((ijk(3) - 1) * m % dimension(2) + (ijk(2) - 1)) &
* m % dimension(1) + ijk(1)
end if
end function mesh_indices_to_bin
!===============================================================================
! BIN_TO_MESH_INDICES maps a single mesh bin from a TallyObject results array to
! (i,j) or (i,j,k) indices
! (i), (i,j), or (i,j,k) indices
!===============================================================================
pure subroutine bin_to_mesh_indices(m, bin, ijk)
@ -122,19 +109,16 @@ contains
integer, intent(in) :: bin
integer, intent(out) :: ijk(:)
integer :: n_x ! number of mesh cells in x direction
integer :: n_y ! number of mesh cells in y direction
n_x = m % dimension(1)
n_y = m % dimension(2)
if (m % n_dimension == 2) then
ijk(1) = mod(bin - 1, n_x) + 1
ijk(2) = (bin - 1)/n_x + 1
if (m % n_dimension == 1) then
ijk(1) = bin
else if (m % n_dimension == 2) then
ijk(1) = mod(bin - 1, m % dimension(1)) + 1
ijk(2) = (bin - 1)/m % dimension(1) + 1
else if (m % n_dimension == 3) then
ijk(1) = mod(bin - 1, n_x) + 1
ijk(2) = mod(bin - 1, n_x*n_y)/n_x + 1
ijk(3) = (bin - 1)/(n_x*n_y) + 1
ijk(1) = mod(bin - 1, m % dimension(1)) + 1
ijk(2) = mod(bin - 1, m % dimension(1) * m % dimension(2)) &
/ m % dimension(1) + 1
ijk(3) = (bin - 1)/(m % dimension(1) * m % dimension(2)) + 1
end if
end subroutine bin_to_mesh_indices
@ -248,6 +232,46 @@ contains
! track will score to a mesh tally.
!===============================================================================
pure function mesh_intersects_1d(m, xyz0, xyz1) result(intersects)
type(RegularMesh), intent(in) :: m
real(8), intent(in) :: xyz0(1)
real(8), intent(in) :: xyz1(1)
logical :: intersects
real(8) :: x0 ! track start point
real(8) :: x1 ! track end point
real(8) :: xm0 ! lower-left coordinates of mesh
real(8) :: xm1 ! upper-right coordinates of mesh
! Copy coordinates of starting point
x0 = xyz0(1)
! Copy coordinates of ending point
x1 = xyz1(1)
! Copy coordinates of mesh lower_left
xm0 = m % lower_left(1)
! Copy coordinates of mesh upper_right
xm1 = m % upper_right(1)
! Set default value for intersects
intersects = .false.
! Check if line intersects left surface
if ((x0 < xm0 .and. x1 > xm0) .or. (x0 > xm0 .and. x1 < xm0)) then
intersects = .true.
return
end if
! Check if line intersects right surface
if ((x0 < xm1 .and. x1 > xm1) .or. (x0 > xm1 .and. x1 < xm1)) then
intersects = .true.
return
end if
end function mesh_intersects_1d
pure function mesh_intersects_2d(m, xyz0, xyz1) result(intersects)
type(RegularMesh), intent(in) :: m
real(8), intent(in) :: xyz0(2)

43
src/nuclide_header.F90
View file

@ -190,7 +190,7 @@ module nuclide_header
class(Nuclide), intent(inout) :: this
integer(HID_T), intent(in) :: group_id
type(VectorReal), intent(in) :: temperature ! list of desired temperatures
integer, intent(in) :: method
integer, intent(inout) :: method
real(8), intent(in) :: tolerance
integer :: i
@ -241,11 +241,22 @@ module nuclide_header
call read_dataset(temps_available(i), kT_group, trim(dset_names(i)))
temps_available(i) = temps_available(i) / K_BOLTZMANN
end do
call sort(temps_available)
! If only one temperature is available, revert to nearest temperature
if (size(temps_available) == 1 .and. &
method == TEMPERATURE_INTERPOLATION) then
call warning("Cross sections for " // trim(this % name) // " are only &
&available at one temperature. Reverting to nearest temperature &
&method.")
method = TEMPERATURE_NEAREST
end if
! Determine actual temperatures to read
select case (method)
case (TEMPERATURE_NEAREST)
! Determine actual temperatures to read
TEMP_LOOP: do i = 1, temperature % size()
! Find nearest temperatures
do i = 1, temperature % size()
temp_desired = temperature % data(i)
i_closest = minloc(abs(temps_available - temp_desired), dim=1)
temp_actual = temps_available(i_closest)
@ -265,11 +276,31 @@ module nuclide_header
&for " // trim(this % name) // " at or near " // &
trim(to_str(nint(temp_desired))) // " K.")
end if
end do TEMP_LOOP
end do
case (TEMPERATURE_INTERPOLATION)
! TODO: Get bounding temperatures
call fatal_error("Temperature interpolation not yet implemented")
! If temperature interpolation or multipole is selected, get a list of
! bounding temperatures for each actual temperature present in the model
TEMP_LOOP: do i = 1, temperature % size()
temp_desired = temperature % data(i)
do j = 1, size(temps_available) - 1
if (temps_available(j) <= temp_desired .and. &
temp_desired < temps_available(j + 1)) then
if (find(temps_to_read, nint(temps_available(j))) == -1) then
call temps_to_read % push_back(nint(temps_available(j)))
end if
if (find(temps_to_read, nint(temps_available(j + 1))) == -1) then
call temps_to_read % push_back(nint(temps_available(j + 1)))
end if
cycle TEMP_LOOP
end if
end do
call fatal_error("Nuclear data library does not contain cross sections &
&for " // trim(this % name) // " at temperatures that bound " // &
trim(to_str(nint(temp_desired))) // " K.")
end do TEMP_LOOP
case (TEMPERATURE_MULTIPOLE)
! Add first available temperature

250
src/output.F90
View file

@ -735,6 +735,7 @@ contains
score_names(abs(SCORE_NU_SCATTER_N)) = "Scattering Prod. Rate Moment"
score_names(abs(SCORE_NU_SCATTER_PN)) = "Scattering Prod. Rate Moment"
score_names(abs(SCORE_NU_SCATTER_YN)) = "Scattering Prod. Rate Moment"
score_names(abs(SCORE_DECAY_RATE)) = "Decay Rate"
score_names(abs(SCORE_DELAYED_NU_FISSION)) = "Delayed-Nu-Fission Rate"
score_names(abs(SCORE_PROMPT_NU_FISSION)) = "Prompt-Nu-Fission Rate"
score_names(abs(SCORE_INVERSE_VELOCITY)) = "Flux-Weighted Inverse Velocity"
@ -938,16 +939,15 @@ contains
type(TallyObject), intent(in) :: t
integer, intent(in) :: unit_tally
integer :: i ! mesh index for x
integer :: j ! mesh index for y
integer :: k ! mesh index for z
integer :: i ! mesh index
integer :: ijk(3) ! indices of mesh cells
integer :: n_dim ! number of mesh dimensions
integer :: n_cells ! number of mesh cells
integer :: l ! index for energy
integer :: i_filter_mesh ! index for mesh filter
integer :: i_filter_ein ! index for incoming energy filter
integer :: i_filter_surf ! index for surface filter
integer :: n ! number of incoming energy bins
integer :: len1 ! length of string
integer :: len2 ! length of string
integer :: filter_index ! index in results array for filters
logical :: print_ebin ! should incoming energy bin be displayed?
character(MAX_LINE_LEN) :: string
@ -974,135 +974,147 @@ contains
n = 1
end if
do i = 1, m % dimension(1)
string = "Mesh Index (" // trim(to_str(i)) // ", "
len1 = len_trim(string)
do j = 1, m % dimension(2)
string = string(1:len1+1) // trim(to_str(j)) // ", "
len2 = len_trim(string)
do k = 1, m % dimension(3)
! Write mesh cell index
string = string(1:len2+1) // trim(to_str(k)) // ")"
write(UNIT=unit_tally, FMT='(1X,A)') trim(string)
! Get the dimensions and number of cells in the mesh
n_dim = m % n_dimension
n_cells = product(m % dimension)
do l = 1, n
if (print_ebin) then
! Set incoming energy bin
matching_bins(i_filter_ein) = l
! Loop over all the mesh cells
do i = 1, n_cells
! Write incoming energy bin
write(UNIT=unit_tally, FMT='(3X,A)') &
trim(t % filters(i_filter_ein) % obj % text_label( &
matching_bins(i_filter_ein)))
end if
! Get the indices for this cell
call bin_to_mesh_indices(m, i, ijk)
matching_bins(i_filter_mesh) = i
! Get the bin for this mesh cell
matching_bins(i_filter_mesh) = &
mesh_indices_to_bin(m, (/ i, j, k /))
! Write the header for this cell
if (n_dim == 1) then
string = "Mesh Index (" // trim(to_str(ijk(1))) // ")"
else if (n_dim == 2) then
string = "Mesh Index (" // trim(to_str(ijk(1))) // ", " &
// trim(to_str(ijk(2))) // ")"
else if (n_dim == 3) then
string = "Mesh Index (" // trim(to_str(ijk(1))) // ", " &
// trim(to_str(ijk(2))) // ", " // trim(to_str(ijk(3))) // ")"
end if
! Left Surface
matching_bins(i_filter_surf) = OUT_LEFT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Left", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
write(UNIT=unit_tally, FMT='(1X,A)') trim(string)
matching_bins(i_filter_surf) = IN_LEFT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Left", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
do l = 1, n
if (print_ebin) then
! Set incoming energy bin
matching_bins(i_filter_ein) = l
! Right Surface
matching_bins(i_filter_surf) = OUT_RIGHT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Right", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Write incoming energy bin
write(UNIT=unit_tally, FMT='(3X,A)') &
trim(t % filters(i_filter_ein) % obj % text_label( &
matching_bins(i_filter_ein)))
end if
matching_bins(i_filter_surf) = IN_RIGHT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Right", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Left Surface
matching_bins(i_filter_surf) = OUT_LEFT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Left", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Back Surface
matching_bins(i_filter_surf) = OUT_BACK
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Back", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_LEFT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Left", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_BACK
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Back", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Right Surface
matching_bins(i_filter_surf) = OUT_RIGHT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Right", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Front Surface
matching_bins(i_filter_surf) = OUT_FRONT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Net Current on Front", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_RIGHT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Right", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_FRONT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Net Current on Front", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
if (n_dim >= 2) then
! Bottom Surface
matching_bins(i_filter_surf) = OUT_BOTTOM
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Bottom", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Back Surface
matching_bins(i_filter_surf) = OUT_BACK
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Back", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_BOTTOM
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Bottom", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_BACK
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Back", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Top Surface
matching_bins(i_filter_surf) = OUT_TOP
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Top", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Front Surface
matching_bins(i_filter_surf) = OUT_FRONT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Net Current on Front", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_TOP
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Top", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
end do
end do
matching_bins(i_filter_surf) = IN_FRONT
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Net Current on Front", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
end if
if (n_dim == 3) then
! Bottom Surface
matching_bins(i_filter_surf) = OUT_BOTTOM
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Bottom", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_BOTTOM
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Bottom", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
! Top Surface
matching_bins(i_filter_surf) = OUT_TOP
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Outgoing Current on Top", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
matching_bins(i_filter_surf) = IN_TOP
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1
write(UNIT=unit_tally, FMT='(5X,A,T35,A,"+/- ",A)') &
"Incoming Current on Top", &
to_str(t % results(1,filter_index) % sum), &
trim(to_str(t % results(1,filter_index) % sum_sq))
end if
end do
end do

71
src/sab_header.F90
View file

@ -80,10 +80,11 @@ module sab_header
contains
subroutine salphabeta_from_hdf5(this, group_id, temperature, tolerance)
subroutine salphabeta_from_hdf5(this, group_id, temperature, method, tolerance)
class(SAlphaBeta), intent(inout) :: this
integer(HID_T), intent(in) :: group_id
type(VectorReal), intent(in) :: temperature ! list of temperatures
integer, intent(in) :: method
real(8), intent(in) :: tolerance
integer :: i, j
@ -142,25 +143,55 @@ contains
call read_dataset(temps_available(i), kT_group, trim(dset_names(i)))
temps_available(i) = temps_available(i) / K_BOLTZMANN
end do
call sort(temps_available)
! Determine actual temperatures to read
TEMP_LOOP: do i = 1, temperature % size()
temp_desired = temperature % data(i)
i_closest = minloc(abs(temps_available - temp_desired), dim=1)
temp_actual = temps_available(i_closest)
if (abs(temp_actual - temp_desired) < tolerance) then
if (find(temps_to_read, nint(temp_actual)) == -1) then
call temps_to_read % push_back(nint(temp_actual))
select case (method)
case (TEMPERATURE_NEAREST)
! Determine actual temperatures to read
do i = 1, temperature % size()
temp_desired = temperature % data(i)
i_closest = minloc(abs(temps_available - temp_desired), dim=1)
temp_actual = temps_available(i_closest)
if (abs(temp_actual - temp_desired) < tolerance) then
if (find(temps_to_read, nint(temp_actual)) == -1) then
call temps_to_read % push_back(nint(temp_actual))
end if
else
call fatal_error("Nuclear data library does not contain cross sections &
&for " // trim(this % name) // " at or near " // &
trim(to_str(nint(temp_desired))) // " K.")
end if
else
call fatal_error("Nuclear data library does not contain cross sections &
&for " // trim(this % name) // " at or near " // &
trim(to_str(nint(temp_desired))) // " K.")
end if
end do TEMP_LOOP
end do
! TODO: If using interpolation, add a block to add bounding temperatures for
! each
case (TEMPERATURE_INTERPOLATION)
! If temperature interpolation or multipole is selected, get a list of
! bounding temperatures for each actual temperature present in the model
TEMP_LOOP: do i = 1, temperature % size()
temp_desired = temperature % data(i)
do j = 1, size(temps_available) - 1
if (temps_available(j) <= temp_desired .and. &
temp_desired < temps_available(j + 1)) then
if (find(temps_to_read, nint(temps_available(j))) == -1) then
call temps_to_read % push_back(nint(temps_available(j)))
end if
if (find(temps_to_read, nint(temps_available(j + 1))) == -1) then
call temps_to_read % push_back(nint(temps_available(j + 1)))
end if
cycle TEMP_LOOP
end if
end do
call fatal_error("Nuclear data library does not contain cross sections &
&for " // trim(this % name) // " at temperatures that bound " // &
trim(to_str(nint(temp_desired))) // " K.")
end do TEMP_LOOP
case (TEMPERATURE_MULTIPOLE)
! Add first available temperature
call temps_to_read % push_back(nint(temps_available(1)))
end select
! Sort temperatures to read
call sort(temps_to_read)
@ -301,6 +332,12 @@ contains
end do
end associate
end do
! Clear data on correlated angle-energy object
deallocate(correlated_dist % breakpoints)
deallocate(correlated_dist % interpolation)
deallocate(correlated_dist % energy)
deallocate(correlated_dist % distribution)
end if
call close_group(inelastic_group)

242
src/tally.F90
View file

@ -12,7 +12,8 @@ module tally
use math, only: t_percentile, calc_pn, calc_rn
use mesh, only: get_mesh_bin, bin_to_mesh_indices, &
get_mesh_indices, mesh_indices_to_bin, &
mesh_intersects_2d, mesh_intersects_3d
mesh_intersects_1d, mesh_intersects_2d, &
mesh_intersects_3d
use mesh_header, only: RegularMesh
use output, only: header
use particle_header, only: LocalCoord, Particle
@ -94,6 +95,8 @@ contains
integer :: score_bin ! scoring bin, e.g. SCORE_FLUX
integer :: score_index ! scoring bin index
integer :: d ! delayed neutron index
integer :: g ! delayed neutron index
integer :: k ! loop index for bank sites
integer :: d_bin ! delayed group bin index
integer :: dg_filter ! index of delayed group filter
real(8) :: yield ! delayed neutron yield
@ -671,6 +674,141 @@ contains
end if
case (SCORE_DECAY_RATE)
! Set the delayedgroup filter index
dg_filter = t % find_filter(FILTER_DELAYEDGROUP)
if (survival_biasing) then
! No fission events occur if survival biasing is on -- need to
! calculate fraction of absorptions that would have resulted in
! delayed-nu-fission
if (micro_xs(p % event_nuclide) % absorption > ZERO .and. &
nuclides(p % event_nuclide) % fissionable) then
! Check if the delayed group filter is present
if (dg_filter > 0) then
select type(filt => t % filters(dg_filter) % obj)
type is (DelayedGroupFilter)
! Loop over all delayed group bins and tally to them
! individually
do d_bin = 1, filt % n_bins
! Get the delayed group for this bin
d = filt % groups(d_bin)
! Compute the yield for this delayed group
yield = nuclides(p % event_nuclide) &
% nu(E, EMISSION_DELAYED, d)
associate (rxn => nuclides(p % event_nuclide) % &
reactions(nuclides(p % event_nuclide) % index_fission(1)))
! Compute the score
score = p % absorb_wgt * yield * &
micro_xs(p % event_nuclide) % fission &
/ micro_xs(p % event_nuclide) % absorption &
* rxn % products(1 + d) % decay_rate
end associate
! Tally to bin
call score_fission_delayed_dg(t, d_bin, score, score_index)
end do
cycle SCORE_LOOP
end select
else
! If the delayed group filter is not present, compute the score
! by accumulating the absorbed weight times the decay rate times
! the fraction of the delayed-nu-fission xs to the absorption xs
! for all delayed groups.
score = ZERO
associate (rxn => nuclides(p % event_nuclide) % &
reactions(nuclides(p % event_nuclide) % index_fission(1)))
! We need to be careful not to overshoot the number of delayed
! groups since this could cause the range of the rxn % products
! array to be exceeded. Hence, we use the size of this array
! and not the MAX_DELAYED_GROUPS constant for this loop.
do d = 1, size(rxn % products) - 2
score = score + rxn % products(1 + d) % decay_rate * &
p % absorb_wgt * micro_xs(p % event_nuclide) % fission *&
nuclides(p % event_nuclide) % nu(E, EMISSION_DELAYED, d)&
/ micro_xs(p % event_nuclide) % absorption
end do
end associate
end if
end if
else
! Skip any non-fission events
if (.not. p % fission) cycle SCORE_LOOP
! If there is no outgoing energy filter, than we only need to
! score to one bin. For the score to be 'analog', we need to
! score the number of particles that were banked in the fission
! bank. Since this was weighted by 1/keff, we multiply by keff
! to get the proper score. Loop over the neutrons produced from
! fission and check which ones are delayed. If a delayed neutron is
! encountered, add its contribution to the fission bank to the
! score.
score = ZERO
! loop over number of particles banked
do k = 1, p % n_bank
! get the delayed group
g = fission_bank(n_bank - p % n_bank + k) % delayed_group
! Case for tallying delayed emissions
if (g /= 0) then
! Accumulate the decay rate times delayed nu fission score
associate (rxn => nuclides(p % event_nuclide) % &
reactions(nuclides(p % event_nuclide) % index_fission(1)))
! determine score based on bank site weight and keff.
score = score + keff * fission_bank(n_bank - p % n_bank + k) &
% wgt * rxn % products(1 + g) % decay_rate
end associate
! if the delayed group filter is present, tally to corresponding
! delayed group bin if it exists
if (dg_filter > 0) then
! declare the delayed group filter type
select type(filt => t % filters(dg_filter) % obj)
type is (DelayedGroupFilter)
! loop over delayed group bins until the corresponding bin is
! found
do d_bin = 1, filt % n_bins
d = filt % groups(d_bin)
! check whether the delayed group of the particle is equal to
! the delayed group of this bin
if (d == g) then
call score_fission_delayed_dg(t, d_bin, score, score_index)
end if
end do
end select
! Reset the score to zero
score = ZERO
end if
end if
end do
! If the delayed group filter is present, cycle because the
! score_fission_delayed_dg(...) has already tallied the score
if (dg_filter > 0) then
cycle SCORE_LOOP
end if
end if
case (SCORE_KAPPA_FISSION)
! Determine kappa-fission cross section on the fly. The ENDF standard
! (ENDF-102) states that MT 18 stores the fission energy as the Q_value
@ -2326,6 +2464,7 @@ contains
integer :: i
integer :: i_tally
integer :: j ! loop indices
integer :: n_dim ! num dimensions of the mesh
integer :: d1 ! dimension index
integer :: d2 ! dimension index
integer :: d3 ! dimension index
@ -2345,6 +2484,7 @@ contains
real(8) :: filt_score ! score applied by filters
logical :: start_in_mesh ! particle's starting xyz in mesh?
logical :: end_in_mesh ! particle's ending xyz in mesh?
logical :: cross_surface ! whether the particle crosses a surface
type(TallyObject), pointer :: t
type(RegularMesh), pointer :: m
@ -2368,14 +2508,18 @@ contains
m => meshes(filt % mesh)
end select
n_dim = m % n_dimension
! Determine indices for starting and ending location
call get_mesh_indices(m, xyz0, ijk0(:m % n_dimension), start_in_mesh)
call get_mesh_indices(m, xyz1, ijk1(:m % n_dimension), end_in_mesh)
call get_mesh_indices(m, xyz0, ijk0, start_in_mesh)
call get_mesh_indices(m, xyz1, ijk1, end_in_mesh)
! Check to see if start or end is in mesh -- if not, check if track still
! intersects with mesh
if ((.not. start_in_mesh) .and. (.not. end_in_mesh)) then
if (m % n_dimension == 2) then
if (n_dim == 1) then
if (.not. mesh_intersects_1d(m, xyz0, xyz1)) cycle
else if (n_dim == 2) then
if (.not. mesh_intersects_2d(m, xyz0, xyz1)) cycle
else
if (.not. mesh_intersects_3d(m, xyz0, xyz1)) cycle
@ -2383,7 +2527,7 @@ contains
end if
! Calculate number of surface crossings
n_cross = sum(abs(ijk1 - ijk0))
n_cross = sum(abs(ijk1(:n_dim) - ijk0(:n_dim)))
if (n_cross == 0) then
cycle
end if
@ -2401,7 +2545,7 @@ contains
end if
! Bounding coordinates
do d1 = 1, 3
do d1 = 1, n_dim
if (uvw(d1) > 0) then
xyz_cross(d1) = m % lower_left(d1) + ijk0(d1) * m % width(d1)
else
@ -2413,10 +2557,13 @@ contains
! Reset scoring bin index
matching_bins(i_filter_surf) = 0
! Set the distances to infinity
d = INFINITY
! Calculate distance to each bounding surface. We need to treat
! special case where the cosine of the angle is zero since this would
! result in a divide-by-zero.
do d1 = 1, 3
do d1 = 1, n_dim
if (uvw(d1) == 0) then
d(d1) = INFINITY
else
@ -2430,11 +2577,16 @@ contains
distance = minval(d)
! Loop over the dimensions
do d1 = 1, 3
do d1 = 1, n_dim
! Get the other dimensions
d2 = mod(d1, 3) + 1
d3 = mod(d1 + 1, 3) + 1
! Get the other dimensions.
if (d1 == 1) then
d2 = mod(d1, 3) + 1
d3 = mod(d1 + 1, 3) + 1
else
d2 = mod(d1 + 1, 3) + 1
d3 = mod(d1, 3) + 1
end if
! Check whether distance is the shortest distance
if (distance == d(d1)) then
@ -2443,8 +2595,9 @@ contains
if (uvw(d1) > 0) then
! Outward current on d1 max surface
if (all(ijk0 >= 1) .and. all(ijk0 <= m % dimension)) then
matching_bins(i_filter_surf) = d1 * 2
if (all(ijk0(:n_dim) >= 1) .and. &
all(ijk0(:n_dim) <= m % dimension)) then
matching_bins(i_filter_surf) = d1 * 4 - 1
matching_bins(i_filter_mesh) = &
mesh_indices_to_bin(m, ijk0)
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
@ -2455,11 +2608,32 @@ contains
end if
! Inward current on d1 min surface
if (ijk0(d1) >= 0 .and. ijk0(d1) < m % dimension(d1) .and. &
ijk0(d2) >= 1 .and. ijk0(d2) <= m % dimension(d2) .and. &
ijk0(d3) >= 1 .and. ijk0(d3) <= m % dimension(d3)) then
cross_surface = .false.
select case(n_dim)
case (1)
if (ijk0(d1) >= 0 .and. ijk0(d1) < m % dimension(d1)) then
cross_surface = .true.
end if
case (2)
if (ijk0(d1) >= 0 .and. ijk0(d1) < m % dimension(d1) .and. &
ijk0(d2) >= 1 .and. ijk0(d2) <= m % dimension(d2)) then
cross_surface = .true.
end if
case (3)
if (ijk0(d1) >= 0 .and. ijk0(d1) < m % dimension(d1) .and. &
ijk0(d2) >= 1 .and. ijk0(d2) <= m % dimension(d2) .and. &
ijk0(d3) >= 1 .and. ijk0(d3) <= m % dimension(d3)) then
cross_surface = .true.
end if
end select
! If the particle crossed the surface, tally the current
if (cross_surface) then
ijk0(d1) = ijk0(d1) + 1
matching_bins(i_filter_surf) = d1 * 2 + 5
matching_bins(i_filter_surf) = d1 * 4 - 2
matching_bins(i_filter_mesh) = &
mesh_indices_to_bin(m, ijk0)
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
@ -2477,8 +2651,9 @@ contains
else
! Outward current on d1 min surface
if (all(ijk0 >= 1) .and. all(ijk0 <= m % dimension)) then
matching_bins(i_filter_surf) = d1 * 2 - 1
if (all(ijk0(:n_dim) >= 1) .and. &
all(ijk0(:n_dim) <= m % dimension)) then
matching_bins(i_filter_surf) = d1 * 4 - 3
matching_bins(i_filter_mesh) = &
mesh_indices_to_bin(m, ijk0)
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &
@ -2489,11 +2664,32 @@ contains
end if
! Inward current on d1 max surface
if (ijk0(d1) > 1 .and. ijk0(d1) <= m % dimension(d1) + 1 .and. &
ijk0(d2) >= 1 .and. ijk0(d2) <= m % dimension(d2) .and. &
ijk0(d3) >= 1 .and. ijk0(d3) <= m % dimension(d3)) then
cross_surface = .false.
select case(n_dim)
case (1)
if (ijk0(d1) > 1 .and. ijk0(d1) <= m % dimension(d1) + 1) then
cross_surface = .true.
end if
case (2)
if (ijk0(d1) > 1 .and. ijk0(d1) <= m % dimension(d1) + 1 .and.&
ijk0(d2) >= 1 .and. ijk0(d2) <= m % dimension(d2)) then
cross_surface = .true.
end if
case (3)
if (ijk0(d1) > 1 .and. ijk0(d1) <= m % dimension(d1) + 1 .and.&
ijk0(d2) >= 1 .and. ijk0(d2) <= m % dimension(d2) .and. &
ijk0(d3) >= 1 .and. ijk0(d3) <= m % dimension(d3)) then
cross_surface = .true.
end if
end select
! If the particle crossed the surface, tally the current
if (cross_surface) then
ijk0(d1) = ijk0(d1) - 1
matching_bins(i_filter_surf) = d1 * 2 + 6
matching_bins(i_filter_surf) = d1 * 4
matching_bins(i_filter_mesh) = &
mesh_indices_to_bin(m, ijk0)
filter_index = sum((matching_bins(1:size(t % filters)) - 1) &

14
src/tally_filter.F90
View file

@ -9,7 +9,8 @@ module tally_filter
use mesh_header, only: RegularMesh
use mesh, only: get_mesh_bin, bin_to_mesh_indices, &
get_mesh_indices, mesh_indices_to_bin, &
mesh_intersects_2d, mesh_intersects_3d
mesh_intersects_1d, mesh_intersects_2d, &
mesh_intersects_3d
use particle_header, only: Particle
use string, only: to_str
use tally_filter_header, only: TallyFilter, TallyFilterContainer
@ -261,7 +262,12 @@ contains
! intersects any part of the mesh.
if (current_bin == NO_BIN_FOUND) then
if ((.not. start_in_mesh) .and. (.not. end_in_mesh)) then
if (m % n_dimension == 2) then
if (m % n_dimension == 1) then
if (.not. mesh_intersects_1d(m, xyz0, xyz1)) then
next_bin = NO_BIN_FOUND
return
end if
else if (m % n_dimension == 2) then
if (.not. mesh_intersects_2d(m, xyz0, xyz1)) then
next_bin = NO_BIN_FOUND
return
@ -427,7 +433,9 @@ contains
m => meshes(this % mesh)
allocate(ijk(m % n_dimension))
call bin_to_mesh_indices(m, bin, ijk)
if (m % n_dimension == 2) then
if (m % n_dimension == 1) then
label = "Mesh Index (" // trim(to_str(ijk(1))) // ")"
elseif (m % n_dimension == 2) then
label = "Mesh Index (" // trim(to_str(ijk(1))) // ", " // &
trim(to_str(ijk(2))) // ")"
elseif (m % n_dimension == 3) then

177
src/trigger.F90
View file

@ -8,7 +8,7 @@ module trigger
use global
use string, only: to_str
use output, only: warning, write_message
use mesh, only: mesh_indices_to_bin
use mesh, only: bin_to_mesh_indices
use mesh_header, only: RegularMesh
use trigger_header, only: TriggerObject
use tally, only: TallyObject
@ -282,9 +282,10 @@ contains
subroutine compute_tally_current(t, trigger)
integer :: i ! mesh index for x
integer :: j ! mesh index for y
integer :: k ! mesh index for z
integer :: i ! mesh index
integer :: ijk(3) ! indices of mesh cells
integer :: n_dim ! number of mesh dimensions
integer :: n_cells ! number of mesh cells
integer :: l ! index for energy
integer :: i_filter_mesh ! index for mesh filter
integer :: i_filter_ein ! index for incoming energy filter
@ -319,99 +320,101 @@ contains
n = 1
end if
do i = 1, m % dimension(1)
do j = 1, m % dimension(2)
do k = 1, m % dimension(3)
do l = 1, n
! Get the dimensions and number of cells in the mesh
n_dim = m % n_dimension
n_cells = product(m % dimension)
if (print_ebin) then
matching_bins(i_filter_ein) = l
end if
! Loop over all the mesh cells
do i = 1, n_cells
matching_bins(i_filter_mesh) = &
mesh_indices_to_bin(m, (/ i, j, k /))
! Get the indices for this cell
call bin_to_mesh_indices(m, i, ijk)
matching_bins(i_filter_mesh) = i
! Left Surface
matching_bins(i_filter_surf) = OUT_LEFT
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = std_dev**2
do l = 1, n
! Right Surface
matching_bins(i_filter_surf) = OUT_RIGHT
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
if (print_ebin) then
matching_bins(i_filter_ein) = l
end if
! Back Surface
matching_bins(i_filter_surf) = OUT_BACK
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Left Surface
matching_bins(i_filter_surf) = OUT_LEFT
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = std_dev**2
! Front Surface
matching_bins(i_filter_surf) = OUT_FRONT
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Right Surface
matching_bins(i_filter_surf) = OUT_RIGHT
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Bottom Surface
matching_bins(i_filter_surf) = OUT_BOTTOM
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Back Surface
matching_bins(i_filter_surf) = OUT_BACK
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Top Surface
matching_bins(i_filter_surf) = OUT_TOP
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Front Surface
matching_bins(i_filter_surf) = OUT_FRONT
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
end do
! Bottom Surface
matching_bins(i_filter_surf) = OUT_BOTTOM
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
! Top Surface
matching_bins(i_filter_surf) = OUT_TOP
filter_index = &
sum((matching_bins(1:size(t % filters)) - 1) * t % stride) + 1
call get_trigger_uncertainty(std_dev, rel_err, 1, filter_index, t)
if (trigger % std_dev < std_dev) then
trigger % std_dev = std_dev
end if
if (trigger % rel_err < rel_err) then
trigger % rel_err = rel_err
end if
trigger % variance = trigger % std_dev**2
end do
end do
end do

2
src/volume_calc.F90
View file

@ -389,7 +389,7 @@ contains
allocate(temp(size(this % domain_id), k))
temp(:, 1:nm) = hits(:, 1:nm)
call move_alloc(FROM=temp, TO=indices)
call move_alloc(FROM=temp, TO=hits)
end if
! Add an entry to both the indices list and the hits list

184
tests/test_cmfd_feed/results_true.dat
View file

@ -126,8 +126,18 @@ tally 3:
tally 4:
3.049469E+00
4.677325E-01
0.000000E+00
0.000000E+00
2.770358E+00
3.879191E-01
5.514939E+00
1.528899E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
@ -140,28 +150,10 @@ tally 4:
0.000000E+00
5.514939E+00
1.528899E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.514939E+00
1.528899E+00
2.770358E+00
3.879191E-01
5.032131E+00
1.275040E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
2.770358E+00
3.879191E-01
7.294002E+00
2.675589E+00
0.000000E+00
@ -172,20 +164,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.294002E+00
2.675589E+00
5.032131E+00
1.275040E+00
7.036008E+00
2.490719E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.032131E+00
1.275040E+00
8.668860E+00
3.776102E+00
0.000000E+00
@ -196,20 +188,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.668860E+00
3.776102E+00
7.036008E+00
2.490719E+00
8.352414E+00
3.501945E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.036008E+00
2.490719E+00
9.345868E+00
4.380719E+00
0.000000E+00
@ -220,20 +212,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.345868E+00
4.380719E+00
8.352414E+00
3.501945E+00
9.093766E+00
4.158282E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.352414E+00
3.501945E+00
9.223771E+00
4.270119E+00
0.000000E+00
@ -244,20 +236,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.223771E+00
4.270119E+00
9.093766E+00
4.158282E+00
9.219150E+00
4.264346E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.093766E+00
4.158282E+00
8.530966E+00
3.651778E+00
0.000000E+00
@ -268,20 +260,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.530966E+00
3.651778E+00
9.219150E+00
4.264346E+00
8.690373E+00
3.785262E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.219150E+00
4.264346E+00
7.204424E+00
2.604203E+00
0.000000E+00
@ -292,20 +284,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.204424E+00
2.604203E+00
8.690373E+00
3.785262E+00
7.513640E+00
2.833028E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.690373E+00
3.785262E+00
5.326721E+00
1.426975E+00
0.000000E+00
@ -316,20 +308,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.326721E+00
1.426975E+00
7.513640E+00
2.833028E+00
5.661144E+00
1.607138E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.513640E+00
2.833028E+00
2.847310E+00
4.090440E-01
0.000000E+00
@ -340,8 +332,18 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
2.847310E+00
4.090440E-01
5.661144E+00
1.607138E+00
3.025812E+00
4.597241E-01
0.000000E+00
@ -352,8 +354,6 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
5.661144E+00
1.607138E+00
0.000000E+00
0.000000E+00
0.000000E+00

184
tests/test_cmfd_nofeed/results_true.dat
View file

@ -126,8 +126,18 @@ tally 3:
tally 4:
3.090000E+00
4.810640E-01
0.000000E+00
0.000000E+00
2.833000E+00
4.078910E-01
5.555000E+00
1.551579E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
@ -140,28 +150,10 @@ tally 4:
0.000000E+00
5.555000E+00
1.551579E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.555000E+00
1.551579E+00
2.833000E+00
4.078910E-01
5.095000E+00
1.310819E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
2.833000E+00
4.078910E-01
7.271000E+00
2.659755E+00
0.000000E+00
@ -172,20 +164,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.271000E+00
2.659755E+00
5.095000E+00
1.310819E+00
7.026000E+00
2.486552E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.095000E+00
1.310819E+00
8.577000E+00
3.703215E+00
0.000000E+00
@ -196,20 +188,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.577000E+00
3.703215E+00
7.026000E+00
2.486552E+00
8.572000E+00
3.680852E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.026000E+00
2.486552E+00
9.393000E+00
4.422429E+00
0.000000E+00
@ -220,20 +212,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.393000E+00
4.422429E+00
8.572000E+00
3.680852E+00
9.261000E+00
4.304411E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.572000E+00
3.680852E+00
9.265000E+00
4.305625E+00
0.000000E+00
@ -244,20 +236,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.265000E+00
4.305625E+00
9.261000E+00
4.304411E+00
9.303000E+00
4.350791E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.261000E+00
4.304411E+00
8.535000E+00
3.659395E+00
0.000000E+00
@ -268,20 +260,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.535000E+00
3.659395E+00
9.303000E+00
4.350791E+00
8.693000E+00
3.799545E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
9.303000E+00
4.350791E+00
7.104000E+00
2.544182E+00
0.000000E+00
@ -292,20 +284,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.104000E+00
2.544182E+00
8.693000E+00
3.799545E+00
7.334000E+00
2.700052E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
8.693000E+00
3.799545E+00
5.168000E+00
1.344390E+00
0.000000E+00
@ -316,20 +308,20 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.168000E+00
1.344390E+00
7.334000E+00
2.700052E+00
5.416000E+00
1.471086E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.334000E+00
2.700052E+00
2.724000E+00
3.745680E-01
0.000000E+00
@ -340,8 +332,18 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
2.724000E+00
3.745680E-01
5.416000E+00
1.471086E+00
2.960000E+00
4.397840E-01
0.000000E+00
@ -352,8 +354,6 @@ tally 4:
0.000000E+00
0.000000E+00
0.000000E+00
5.416000E+00
1.471086E+00
0.000000E+00
0.000000E+00
0.000000E+00

1
tests/test_filter_mesh/inputs_true.dat Normal file
View file

@ -0,0 +1 @@
5a9e65b8a8c9d7c575fc48c5d289bbc805739729a33d83aa79985473d83c8cc3a0c7dad8e95221090917c35ac4842667c8c9daecd06dc6b909a92475f5083753

1
tests/test_filter_mesh/results_true.dat Normal file
View file

@ -0,0 +1 @@
89387dd9e5b962c773e1782ff829846968dc456d899963f5dd98761fbde73a3f81676717ff3599bc26a1b77247826c38756735a9b2b329b80ad66286a62bd3f9

91
tests/test_filter_mesh/test_filter_mesh.py Normal file
View file

@ -0,0 +1,91 @@
#!/usr/bin/env python
import os
import sys
import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import HashedPyAPITestHarness
import openmc
class FilterMeshTestHarness(HashedPyAPITestHarness):
def _build_inputs(self):
# The summary.h5 file needs to be created to read in the tallies
self._input_set.settings.output = {'summary': True}
# Initialize the tallies file
tallies_file = openmc.Tallies()
# Initialize Meshes
mesh_1d = openmc.Mesh(mesh_id=1)
mesh_1d.type = 'regular'
mesh_1d.dimension = [17]
mesh_1d.lower_left = [-182.07]
mesh_1d.upper_right = [182.07]
mesh_2d = openmc.Mesh(mesh_id=2)
mesh_2d.type = 'regular'
mesh_2d.dimension = [17, 17]
mesh_2d.lower_left = [-182.07, -182.07]
mesh_2d.upper_right = [182.07, 182.07]
mesh_3d = openmc.Mesh(mesh_id=3)
mesh_3d.type = 'regular'
mesh_3d.dimension = [17, 17, 17]
mesh_3d.lower_left = [-182.07, -182.07, -183.00]
mesh_3d.upper_right = [182.07, 182.07, 183.00]
# Initialize the filters
mesh_1d_filter = openmc.Filter(type='mesh')
mesh_2d_filter = openmc.Filter(type='mesh')
mesh_3d_filter = openmc.Filter(type='mesh')
mesh_1d_filter.mesh = mesh_1d
mesh_2d_filter.mesh = mesh_2d
mesh_3d_filter.mesh = mesh_3d
# Initialized the tallies
tally = openmc.Tally(name='tally 1')
tally.filters = [mesh_1d_filter]
tally.scores = ['total']
tallies_file.append(tally)
tally = openmc.Tally(name='tally 2')
tally.filters = [mesh_1d_filter]
tally.scores = ['current']
tallies_file.append(tally)
tally = openmc.Tally(name='tally 3')
tally.filters = [mesh_2d_filter]
tally.scores = ['total']
tallies_file.append(tally)
tally = openmc.Tally(name='tally 4')
tally.filters = [mesh_2d_filter]
tally.scores = ['current']
tallies_file.append(tally)
tally = openmc.Tally(name='tally 5')
tally.filters = [mesh_3d_filter]
tally.scores = ['total']
tallies_file.append(tally)
tally = openmc.Tally(name='tally 6')
tally.filters = [mesh_3d_filter]
tally.scores = ['current']
tallies_file.append(tally)
# Export tallies to file
self._input_set.tallies = tallies_file
super(FilterMeshTestHarness, self)._build_inputs()
def _cleanup(self):
super(FilterMeshTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = FilterMeshTestHarness('statepoint.10.*', True)
harness.main()

181
tests/test_filter_mesh_2d/geometry.xml
View file

@ -1,181 +0,0 @@
<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" region=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" region=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" region=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" region=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" region=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" region=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" region=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" region=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" region="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" region="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" region="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" region="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" region="-1" />
<cell id="22" universe="1" material="2" region="1 -2" />
<cell id="23" universe="1" material="3" region="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" region="-3" />
<cell id="25" universe="2" material="2" region="3 -4" />
<cell id="26" universe="2" material="3" region="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" region="-1" />
<cell id="28" universe="3" material="2" region="1 -2" />
<cell id="29" universe="3" material="4" region="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" region="-3" />
<cell id="31" universe="4" material="2" region="3 -4" />
<cell id="32" universe="4" material="4" region="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" region="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" region="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" region="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" region="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<pitch>1.26 1.26</pitch>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<pitch>1.26 1.26</pitch>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<pitch>21.42 21.42</pitch>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<pitch>21.42 21.42</pitch>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

270
tests/test_filter_mesh_2d/materials.xml
View file

@ -1,270 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U234" ao="4.9476e-6" />
<nuclide name="U235" ao="4.8218e-4" />
<nuclide name="U236" ao="9.0402e-5" />
<nuclide name="U238" ao="2.1504e-2" />
<nuclide name="Np237" ao="7.3733e-6" />
<nuclide name="Pu238" ao="1.5148e-6" />
<nuclide name="Pu239" ao="1.3955e-4" />
<nuclide name="Pu240" ao="3.4405e-5" />
<nuclide name="Pu241" ao="2.1439e-5" />
<nuclide name="Pu242" ao="3.7422e-6" />
<nuclide name="Am241" ao="4.5041e-7" />
<nuclide name="Am242_m1" ao="9.2301e-9" />
<nuclide name="Am243" ao="4.7878e-7" />
<nuclide name="Cm242" ao="1.0485e-7" />
<nuclide name="Cm243" ao="1.4268e-9" />
<nuclide name="Cm244" ao="8.8756e-8" />
<nuclide name="Cm245" ao="3.5285e-9" />
<nuclide name="Mo95" ao="2.6497e-5" />
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<!-- Cladding composition -->
<material id="2">
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</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
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<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
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<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
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<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
<material id="5">
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<!-- Lower radial reflector -->
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<nuclide name="H1" wo="0.0095661" />
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<sab name="c_H_in_H2O" />
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<!-- Upper radial reflector / Top plate region -->
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<!-- Bottom plate region -->
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<!-- Bottom nozzle region -->
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<!-- Top of Fuel Assemblies -->
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<!-- Bottom of Fuel Assemblies -->
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</materials>

581
tests/test_filter_mesh_2d/results_true.dat
View file

@ -1,581 +0,0 @@
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1.425606E+00
5.136552E-01
2.638417E-01
7.735493E-01
1.575534E-01
1.453489E+00
6.697189E-01
5.089636E-01
8.836228E-02
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.678278E-01
2.097037E-02
5.208007E-01
2.057626E-01
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
7.532560E-03
5.673946E-05
9.539296E-01
5.206980E-01
0.000000E+00
0.000000E+00
6.927475E-01
2.317744E-01
3.953753E-01
1.420303E-01
1.377786E-01
1.716503E-02
1.441275E+00
5.086865E-01
4.033076E-01
5.492660E-02
8.534416E-01
2.290345E-01
1.422521E+00
6.953668E-01
1.940736E-01
2.763730E-02
0.000000E+00
0.000000E+00
5.312751E-02
1.423243E-03
1.050464E+00
5.524605E-01
5.214580E-02
2.719184E-03
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
3.011069E-02
9.066538E-04
2.913901E+00
1.841912E+00
4.513270E+00
5.611449E+00
5.367404E+00
6.853344E+00
1.137705E+00
5.670907E-01
6.059470E-02
3.671718E-03
0.000000E+00
0.000000E+00
3.374418E-01
1.138670E-01
7.171591E-02
5.143172E-03
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
6.978650E-01
2.584000E-01
1.653243E+00
8.369762E-01
1.237276E+00
4.961691E-01
3.521780E-01
6.575561E-02
3.479381E-01
1.210609E-01
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
5.118696E-02
2.620104E-03
1.451562E-02
2.107031E-04
1.045336E-01
1.092727E-02
5.835684E-02
3.405521E-03
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00

19
tests/test_filter_mesh_2d/settings.xml
View file

@ -1,19 +0,0 @@
<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

16
tests/test_filter_mesh_2d/tallies.xml
View file

@ -1,16 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-182.07 -182.07</lower_left>
<upper_right>182.07 182.07</upper_right>
<dimension>17 17</dimension>
</mesh>
<tally id="1">
<filter type="mesh" bins="1" />
<scores>total</scores>
</tally>
</tallies>

11
tests/test_filter_mesh_2d/test_filter_mesh_2d.py
View file

@ -1,11 +0,0 @@
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import TestHarness
if __name__ == '__main__':
harness = TestHarness('statepoint.10.*', True)
harness.main()

181
tests/test_filter_mesh_3d/geometry.xml
View file

@ -1,181 +0,0 @@
<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.41" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.56" />
<surface id="4" type="z-cylinder" coeffs="0. 0. 0.62" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 187.6" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 209.0" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 229.0" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 249.0" boundary="vacuum" />
<surface id="31" type="z-plane" coeffs="-229.0" boundary="vacuum" />
<surface id="32" type="z-plane" coeffs="-199.0" />
<surface id="33" type="z-plane" coeffs="-193.0" />
<surface id="34" type="z-plane" coeffs="-183.0" />
<surface id="35" type="z-plane" coeffs="0.0" />
<surface id="36" type="z-plane" coeffs="183.0" />
<surface id="37" type="z-plane" coeffs="203.0" />
<surface id="38" type="z-plane" coeffs="215.0" />
<surface id="39" type="z-plane" coeffs="223.0" boundary="vacuum" />
<!-- All geometry on base universe -->
<cell id="1" fill="200" region=" -6 34 -35" /> <!-- Lower core -->
<cell id="2" fill="201" region=" -6 35 -36" /> <!-- Upper core -->
<cell id="3" material="8" region=" -7 31 -32" /> <!-- Lower core plate region -->
<cell id="4" material="9" region=" -5 32 -33" /> <!-- Bottom nozzle region -->
<cell id="5" material="12" region=" -5 33 -34" /> <!-- Bottom FA region -->
<cell id="6" material="11" region=" -5 36 -37" /> <!-- Top FA region -->
<cell id="7" material="10" region=" -5 37 -38" /> <!-- Top nozzle region -->
<cell id="8" material="7" region=" -7 38 -39" /> <!-- Upper plate region -->
<cell id="9" material="4" region="6 -7 32 -38" /> <!-- Downcomer -->
<cell id="10" material="5" region="7 -8 31 -39" /> <!-- RPV -->
<cell id="11" material="6" region="5 -6 32 -34" /> <!-- Bottom of radial reflector -->
<cell id="12" material="7" region="5 -6 36 -38" /> <!-- Top of radial reflector -->
<!-- Fuel pin, cladding, cold water -->
<cell id="21" universe="1" material="1" region="-1" />
<cell id="22" universe="1" material="2" region="1 -2" />
<cell id="23" universe="1" material="3" region="2" />
<!-- Instrumentation guide tube -->
<cell id="24" universe="2" material="3" region="-3" />
<cell id="25" universe="2" material="2" region="3 -4" />
<cell id="26" universe="2" material="3" region="4" />
<!-- Fuel pin, cladding, hot water -->
<cell id="27" universe="3" material="1" region="-1" />
<cell id="28" universe="3" material="2" region="1 -2" />
<cell id="29" universe="3" material="4" region="2" />
<!-- Instrumentation guide tube -->
<cell id="30" universe="4" material="4" region="-3" />
<cell id="31" universe="4" material="2" region="3 -4" />
<cell id="32" universe="4" material="4" region="4" />
<!-- cell for water assembly (cold) -->
<cell id="50" universe="5" material="4" region="34 -35" />
<!-- containing cell for fuel assembly -->
<cell id="60" universe="6" fill="100" region="34 -35" />
<!-- cell for water assembly (hot) -->
<cell id="70" universe="7" material="3" region="35 -36" />
<!-- containing cell for fuel assembly -->
<cell id="80" universe="8" fill="101" region="35 -36" />
<!-- Fuel Assembly (Lower Half) -->
<lattice id="100">
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<pitch>1.26 1.26</pitch>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<!-- Fuel Assembly (Upper Half) -->
<lattice id="101">
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<pitch>1.26 1.26</pitch>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<!-- Core Lattice (Lower Half) -->
<lattice id="200">
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<pitch>21.42 21.42</pitch>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
</universes>
</lattice>
<!-- Core Lattice (Upper Half) -->
<lattice id="201">
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<pitch>21.42 21.42</pitch>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
</universes>
</lattice>
</geometry>

270
tests/test_filter_mesh_3d/materials.xml
View file

@ -1,270 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Fuel composition -->
<material id="1">
<density value="10.062" units="g/cm3" />
<nuclide name="U234" ao="4.9476e-6" />
<nuclide name="U235" ao="4.8218e-4" />
<nuclide name="U236" ao="9.0402e-5" />
<nuclide name="U238" ao="2.1504e-2" />
<nuclide name="Np237" ao="7.3733e-6" />
<nuclide name="Pu238" ao="1.5148e-6" />
<nuclide name="Pu239" ao="1.3955e-4" />
<nuclide name="Pu240" ao="3.4405e-5" />
<nuclide name="Pu241" ao="2.1439e-5" />
<nuclide name="Pu242" ao="3.7422e-6" />
<nuclide name="Am241" ao="4.5041e-7" />
<nuclide name="Am242_m1" ao="9.2301e-9" />
<nuclide name="Am243" ao="4.7878e-7" />
<nuclide name="Cm242" ao="1.0485e-7" />
<nuclide name="Cm243" ao="1.4268e-9" />
<nuclide name="Cm244" ao="8.8756e-8" />
<nuclide name="Cm245" ao="3.5285e-9" />
<nuclide name="Mo95" ao="2.6497e-5" />
<nuclide name="Tc99" ao="3.2772e-5" />
<nuclide name="Ru101" ao="3.0742e-5" />
<nuclide name="Ru103" ao="2.3505e-6" />
<nuclide name="Ag109" ao="2.0009e-6" />
<nuclide name="Xe135" ao="1.0801e-8" />
<nuclide name="Cs133" ao="3.4612e-5" />
<nuclide name="Nd143" ao="2.6078e-5" />
<nuclide name="Nd145" ao="1.9898e-5" />
<nuclide name="Sm147" ao="1.6128e-6" />
<nuclide name="Sm149" ao="1.1627e-7" />
<nuclide name="Sm150" ao="7.1727e-6" />
<nuclide name="Sm151" ao="5.4947e-7" />
<nuclide name="Sm152" ao="3.0221e-6" />
<nuclide name="Eu153" ao="2.6209e-6" />
<nuclide name="Gd155" ao="1.5369e-9" />
<nuclide name="O16" ao="4.5737e-2" />
</material>
<!-- Cladding composition -->
<material id="2">
<density value="5.77" units="g/cm3" />
<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="0.0280" />
</material>
<!-- Cold borated water -->
<material id="3">
<density value="0.07416" units="atom/b-cm" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
<material id="4">
<density value="0.06614" units="atom/b-cm" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
<material id="5">
<density value="7.9" units="g/cm3" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Ni61" wo="0.0001183" />
<nuclide name="Ni62" wo="0.0003835" />
<nuclide name="Ni64" wo="0.0001008" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Mo92" wo="0.000849" />
<nuclide name="Mo94" wo="0.0005418" />
<nuclide name="Mo95" wo="0.0009438" />
<nuclide name="Mo96" wo="0.0010002" />
<nuclide name="Mo97" wo="0.0005796" />
<nuclide name="Mo98" wo="0.0014814" />
<nuclide name="Mo100" wo="0.0006042" />
<nuclide name="Si28" wo="0.00367464" />
<nuclide name="Si29" wo="0.00019336" />
<nuclide name="Si30" wo="0.000132" />
<nuclide name="Cr50" wo="0.00010435" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="Cr53" wo="0.00024185" />
<nuclide name="Cr54" wo="6.1325e-05" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
<nuclide name="Cu65" wo="0.0006304" />
</material>
<!-- Lower radial reflector -->
<material id="6">
<density value="4.32" units="g/cm3" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-5" />
<nuclide name="B11" wo="1.40499e-4" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Ni60" wo="0.022034425592" />
<nuclide name="Ni61" wo="0.000973510811" />
<nuclide name="Ni62" wo="0.003155886695" />
<nuclide name="Ni64" wo="0.000829500336" />
<nuclide name="Mn55" wo="0.0182870" />
<nuclide name="Si28" wo="0.00839976771" />
<nuclide name="Si29" wo="0.00044199679" />
<nuclide name="Si30" wo="0.0003017355" />
<nuclide name="Cr50" wo="0.007251360806" />
<nuclide name="Cr52" wo="0.145407678031" />
<nuclide name="Cr53" wo="0.016806340306" />
<nuclide name="Cr54" wo="0.004261520857" />
<sab name="c_H_in_H2O" />
</material>
<!-- Upper radial reflector / Top plate region -->
<material id="7">
<density value="4.28" units="g/cm3" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-5" />
<nuclide name="B11" wo="1.26481e-4" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Ni60" wo="0.022240333032" />
<nuclide name="Ni61" wo="0.000982608081" />
<nuclide name="Ni62" wo="0.003185377845" />
<nuclide name="Ni64" wo="0.000837251856" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Si28" wo="0.00847831314" />
<nuclide name="Si29" wo="0.00044612986" />
<nuclide name="Si30" wo="0.000304557" />
<nuclide name="Cr50" wo="0.00731912987" />
<nuclide name="Cr52" wo="0.146766614995" />
<nuclide name="Cr53" wo="0.01696340737" />
<nuclide name="Cr54" wo="0.004301347765" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom plate region -->
<material id="8">
<density value="7.184" units="g/cm3" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-6" />
<nuclide name="B11" wo="1.68974e-5" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Ni60" wo="0.023850159704" />
<nuclide name="Ni61" wo="0.001053732407" />
<nuclide name="Ni62" wo="0.003415945715" />
<nuclide name="Ni64" wo="0.000897854832" />
<nuclide name="Mn55" wo="0.0197940" />
<nuclide name="Si28" wo="0.00909197802" />
<nuclide name="Si29" wo="0.00047842098" />
<nuclide name="Si30" wo="0.000326601" />
<nuclide name="Cr50" wo="0.007848910646" />
<nuclide name="Cr52" wo="0.157390026871" />
<nuclide name="Cr53" wo="0.018191270146" />
<nuclide name="Cr54" wo="0.004612692337" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom nozzle region -->
<material id="9">
<density value="2.53" units="g/cm3" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-5" />
<nuclide name="B11" wo="3.59854e-4" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Ni60" wo="0.018811987544" />
<nuclide name="Ni61" wo="0.000831139127" />
<nuclide name="Ni62" wo="0.002694352115" />
<nuclide name="Ni64" wo="0.000708189552" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Si28" wo="0.007171335558" />
<nuclide name="Si29" wo="0.000377356542" />
<nuclide name="Si30" wo="0.0002576079" />
<nuclide name="Cr50" wo="0.006190885148" />
<nuclide name="Cr52" wo="0.124142524198" />
<nuclide name="Cr53" wo="0.014348496148" />
<nuclide name="Cr54" wo="0.003638294506" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top nozzle region -->
<material id="10">
<density value="1.746" units="g/cm3" />
<nuclide name="H1" wo="0.0358870" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="1.15699e-4" />
<nuclide name="B11" wo="5.27075e-4" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Ni60" wo="0.0163554502" />
<nuclide name="Ni61" wo="0.000722605975" />
<nuclide name="Ni62" wo="0.002342513875" />
<nuclide name="Ni64" wo="0.0006157116" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Si28" wo="0.006234853554" />
<nuclide name="Si29" wo="0.000328078746" />
<nuclide name="Si30" wo="0.0002239677" />
<nuclide name="Cr50" wo="0.005382452306" />
<nuclide name="Cr52" wo="0.107931450781" />
<nuclide name="Cr53" wo="0.012474806806" />
<nuclide name="Cr54" wo="0.003163190107" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top of Fuel Assemblies -->
<material id="11">
<density value="3.044" units="g/cm3" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-5" />
<nuclide name="B11" wo="2.39272e-4" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom of Fuel Assemblies -->
<material id="12">
<density value="1.762" units="g/cm3" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-5" />
<nuclide name="B11" wo="4.30120e-4" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>

9829
tests/test_filter_mesh_3d/results_true.dat
View file

File diff suppressed because it is too large Load diff

19
tests/test_filter_mesh_3d/settings.xml
View file

@ -1,19 +0,0 @@
<?xml version="1.0"?>
<settings>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>100</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>
-160 -160 -183
160 160 183
</parameters>
</space>
</source>
</settings>

16
tests/test_filter_mesh_3d/tallies.xml
View file

@ -1,16 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-182.07 -182.07 -183.00</lower_left>
<upper_right>182.07 182.07 183.00</upper_right>
<dimension>17 17 17</dimension>
</mesh>
<tally id="1">
<filter type="mesh" bins="1" />
<scores>total</scores>
</tally>
</tallies>

11
tests/test_filter_mesh_3d/test_filter_mesh_3d.py
View file

@ -1,11 +0,0 @@
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import TestHarness
if __name__ == '__main__':
harness = TestHarness('statepoint.10.*', True)
harness.main()

2
tests/test_mgxs_library_condense/inputs_true.dat
View file

@ -1 +1 @@
2b2a2f5778b03f87d20fa6da96cc19db0489f69d4d5f0cac02dd407fd8e53a082081bfef35c4310cb2e0651254766d499e89279e711fd6fd93f913c964855839
723ce48152faa9ec1576c26a825dfa45cdd858e721bd698d72d559ac3b9e5c37e5048305bd9af9c3137a781798ab2eee20e5df46455bfd9d6819a08fd2bff47d

21
tests/test_mgxs_library_condense/results_true.dat
View file

@ -61,6 +61,13 @@
3 10000 4 1 total 0.002752 0.000240
4 10000 5 1 total 0.001231 0.000105
5 10000 6 1 total 0.000512 0.000044
material delayedgroup group in nuclide mean std. dev.
0 10000 1 1 total 0.000000 0.000000
1 10000 2 1 total 0.032739 0.028454
2 10000 3 1 total 0.120780 0.170809
3 10000 4 1 total 0.302780 0.109110
4 10000 5 1 total 0.000000 0.000000
5 10000 6 1 total 0.000000 0.000000
material group in nuclide mean std. dev.
0 10001 1 total 0.311594 0.013793
material group in nuclide mean std. dev.
@ -123,6 +130,13 @@
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.904999 0.043964
@ -186,4 +200,11 @@
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0

2
tests/test_mgxs_library_distribcell/inputs_true.dat
View file

@ -1 +1 @@
ad427594bd8a68ad35382bc34b5932e7c78480b6e327caf63782d563fd6e6e5fb4e7b0dfd9094394a5db092f789c473dbb08cb6b3d0c0296edcfc247dbe95d6f
7d95d5cf3f4d1f3277d1a1bbc638b47888d7eb1e6afeedea73140ae5caeebead7c5f1a2945f2a18b49ce75adbd9df17773390530fee129d981a3af50141fe116

7
tests/test_mgxs_library_distribcell/results_true.dat
View file

@ -61,3 +61,10 @@
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 4 1 total 0.002727 0.000135
4 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 5 1 total 0.001210 0.000058
5 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 6 1 total 0.000504 0.000024
avg(distribcell) delayedgroup group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.000000 0.000000
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 2 1 total 0.032739 0.046300
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 3 1 total 0.120780 0.170809
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 4 1 total 0.000000 0.000000
4 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 5 1 total 0.000000 0.000000
5 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 6 1 total 2.853000 4.034751

2
tests/test_mgxs_library_hdf5/inputs_true.dat
View file

@ -1 +1 @@
2b2a2f5778b03f87d20fa6da96cc19db0489f69d4d5f0cac02dd407fd8e53a082081bfef35c4310cb2e0651254766d499e89279e711fd6fd93f913c964855839
723ce48152faa9ec1576c26a825dfa45cdd858e721bd698d72d559ac3b9e5c37e5048305bd9af9c3137a781798ab2eee20e5df46455bfd9d6819a08fd2bff47d

39
tests/test_mgxs_library_hdf5/results_true.dat
View file

@ -111,6 +111,19 @@ domain=10000 type=beta
[ 3.21434855e-04 1.09939816e-03]
[ 1.82980497e-04 4.50738567e-04]
[ 7.48899920e-05 1.88812772e-04]]
domain=10000 type=decay-rate
[[ 0. 0. ]
[ 0. 0.032739]
[ 0. 0.12078 ]
[ 0. 0.30278 ]
[ 0. 0. ]
[ 0. 0. ]]
[[ 0. 0. ]
[ 0. 0.02845437]
[ 0. 0.17080871]
[ 0. 0.10910951]
[ 0. 0. ]
[ 0. 0. ]]
domain=10001 type=total
[ 0.31373767 0.3008214 ]
[ 0.0155819 0.02805245]
@ -212,6 +225,19 @@ domain=10001 type=chi-delayed
[ 0. 0.]
[ 0. 0.]]
domain=10001 type=beta
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10001 type=decay-rate
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
@ -337,3 +363,16 @@ domain=10002 type=beta
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10002 type=decay-rate
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]

2
tests/test_mgxs_library_mesh/inputs_true.dat
View file

@ -1 +1 @@
68c7695d7ae0367c59155eab05d3fe859cae895170f2cd32d4463af340a9a2035be16221b1eda8e2a1132bfe1b8163ca8d964fb1b23274c232fb10fd88274aea
88b1a1b52bcae466bab63038d03e9b2fb9f2a28aac3d73573ca00d5f0c116aa9e1c97341215b80266e8317a0549f11d9adcb8726c82fcc1741a5a730e10c8186

26
tests/test_mgxs_library_mesh/results_true.dat
View file

@ -208,3 +208,29 @@
21 2 2 1 4 1 total 0.002143 0.001028
22 2 2 1 5 1 total 0.001026 0.000492
23 2 2 1 6 1 total 0.000408 0.000196
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.00000 0.000000
1 1 1 1 2 1 total 0.00000 0.000000
2 1 1 1 3 1 total 0.00000 0.000000
3 1 1 1 4 1 total 0.30278 0.428196
4 1 1 1 5 1 total 0.00000 0.000000
5 1 1 1 6 1 total 0.00000 0.000000
6 1 2 1 1 1 total 0.00000 0.000000
7 1 2 1 2 1 total 0.00000 0.000000
8 1 2 1 3 1 total 0.00000 0.000000
9 1 2 1 4 1 total 0.00000 0.000000
10 1 2 1 5 1 total 0.00000 0.000000
11 1 2 1 6 1 total 0.00000 0.000000
12 2 1 1 1 1 total 0.00000 0.000000
13 2 1 1 2 1 total 0.00000 0.000000
14 2 1 1 3 1 total 0.00000 0.000000
15 2 1 1 4 1 total 0.00000 0.000000
16 2 1 1 5 1 total 0.00000 0.000000
17 2 1 1 6 1 total 0.00000 0.000000
18 2 2 1 1 1 total 0.00000 0.000000
19 2 2 1 2 1 total 0.00000 0.000000
20 2 2 1 3 1 total 0.00000 0.000000
21 2 2 1 4 1 total 0.00000 0.000000
22 2 2 1 5 1 total 0.00000 0.000000
23 2 2 1 6 1 total 0.00000 0.000000

2
tests/test_mgxs_library_no_nuclides/inputs_true.dat
View file

@ -1 +1 @@
2b2a2f5778b03f87d20fa6da96cc19db0489f69d4d5f0cac02dd407fd8e53a082081bfef35c4310cb2e0651254766d499e89279e711fd6fd93f913c964855839
723ce48152faa9ec1576c26a825dfa45cdd858e721bd698d72d559ac3b9e5c37e5048305bd9af9c3137a781798ab2eee20e5df46455bfd9d6819a08fd2bff47d

39
tests/test_mgxs_library_no_nuclides/results_true.dat
View file

@ -123,6 +123,19 @@
6 10000 4 2 total 0.011426 0.001099
8 10000 5 2 total 0.004684 0.000451
10 10000 6 2 total 0.001962 0.000189
material delayedgroup group in nuclide mean std. dev.
1 10000 1 1 total 0.000000 0.000000
3 10000 2 1 total 0.000000 0.000000
5 10000 3 1 total 0.000000 0.000000
7 10000 4 1 total 0.000000 0.000000
9 10000 5 1 total 0.000000 0.000000
11 10000 6 1 total 0.000000 0.000000
0 10000 1 2 total 0.000000 0.000000
2 10000 2 2 total 0.032739 0.028454
4 10000 3 2 total 0.120780 0.170809
6 10000 4 2 total 0.302780 0.109110
8 10000 5 2 total 0.000000 0.000000
10 10000 6 2 total 0.000000 0.000000
material group in nuclide mean std. dev.
1 10001 1 total 0.313738 0.015582
0 10001 2 total 0.300821 0.028052
@ -247,6 +260,19 @@
4 10001 3 2 total 0.0 0.0
6 10001 4 2 total 0.0 0.0
8 10001 5 2 total 0.0 0.0
10 10001 6 2 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
1 10001 1 1 total 0.0 0.0
3 10001 2 1 total 0.0 0.0
5 10001 3 1 total 0.0 0.0
7 10001 4 1 total 0.0 0.0
9 10001 5 1 total 0.0 0.0
11 10001 6 1 total 0.0 0.0
0 10001 1 2 total 0.0 0.0
2 10001 2 2 total 0.0 0.0
4 10001 3 2 total 0.0 0.0
6 10001 4 2 total 0.0 0.0
8 10001 5 2 total 0.0 0.0
10 10001 6 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10002 1 total 0.664572 0.031215
@ -372,4 +398,17 @@
4 10002 3 2 total 0.0 0.0
6 10002 4 2 total 0.0 0.0
8 10002 5 2 total 0.0 0.0
10 10002 6 2 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
1 10002 1 1 total 0.0 0.0
3 10002 2 1 total 0.0 0.0
5 10002 3 1 total 0.0 0.0
7 10002 4 1 total 0.0 0.0
9 10002 5 1 total 0.0 0.0
11 10002 6 1 total 0.0 0.0
0 10002 1 2 total 0.0 0.0
2 10002 2 2 total 0.0 0.0
4 10002 3 2 total 0.0 0.0
6 10002 4 2 total 0.0 0.0
8 10002 5 2 total 0.0 0.0
10 10002 6 2 total 0.0 0.0

2
tests/test_score_current/results_true.dat
View file

@ -1 +1 @@
6e432700c1fb8641d106471f1fd19a0bf0f00f8b03a97131f2d73732c5a8eea48edf910c7b27b83058a7914c47c29dc7e7899b7dbb83485309b4f7d9f20471d2
05f3d67355e823afe6c8f3a721a2a7b9468f128bd14eace44aa7b85f8b6535e099cb27219dd88b9b1a242d36cc5cefd6d4c4f3549f0463120837e6c6b57650e7

2
tests/test_source/test_source.py
View file

@ -13,7 +13,7 @@ import openmc
class SourceTestHarness(PyAPITestHarness):
def _build_inputs(self):
mat1 = openmc.Material(material_id=1, temperature='294')
mat1 = openmc.Material(material_id=1, temperature=294)
mat1.set_density('g/cm3', 4.5)
mat1.add_nuclide(openmc.Nuclide('U235'), 1.0)
materials = openmc.Materials([mat1])

7
tests/testing_harness.py
View file

@ -344,3 +344,10 @@ class PyAPITestHarness(TestHarness):
for f in output:
if os.path.exists(f):
os.remove(f)
class HashedPyAPITestHarness(PyAPITestHarness):
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
return super(HashedPyAPITestHarness, self)._get_results(True)

2
tests/travis_install.sh
View file

@ -15,7 +15,7 @@ fi
# Build PHDF5
if [[ ! -e $HOME/phdf5_install/bin/h5pfc ]]; then
wget -q http://www.hdfgroup.org/ftp/HDF5/releases/hdf5-1.8.15/src/hdf5-1.8.15.tar.gz
wget -q http://support.hdfgroup.org/ftp/HDF5/releases/hdf5-1.8.15/src/hdf5-1.8.15.tar.gz
tar -xzvf hdf5-1.8.15.tar.gz >/dev/null 2>&1
mv hdf5-1.8.15 phdf5-1.8.15; cd phdf5-1.8.15
CC=$HOME/mpich_install/bin/mpicc FC=$HOME/mpich_install/bin/mpif90 \