Merged with develop and tally triggers

This commit is contained in:
Will Boyd 2015-05-07 17:05:19 -04:00
commit f49749afb3
47 changed files with 2280 additions and 70 deletions

View file

@ -139,6 +139,8 @@ default. This element has the following attributes/sub-elements:
*Default*: 1.0
.. _eigenvalue:
``<eigenvalue>`` Element
------------------------
@ -170,6 +172,34 @@ should be performed. It has the following attributes/sub-elements:
*Default*: None
:keff_trigger:
This tag specifies a precision trigger on the combined :math:`k_{eff}`. The
trigger is a convergence criterion on the uncertainty of the estimated
eigenvalue. It has the following attributes/sub-elements:
:type:
The type of precision trigger. Accepted options are "variance", "std_dev",
and "rel_err".
:variance:
Variance of the batch mean :math:`\sigma^2`
:std_dev:
Standard deviation of the batch mean :math:`\sigma`
:rel_err:
Relative error of the batch mean :math:`\frac{\sigma}{\mu}`
*Default*: None
:threshold:
The precision trigger's convergence criterion for the
combined :math:`k_{eff}`.
*Default*: None
.. note:: See section on the :ref:`trigger` for more information.
``<energy_grid>`` Element
-------------------------
@ -214,8 +244,8 @@ problem. It has the following attributes/sub-elements:
``<fixed_source>`` Element
--------------------------
The ``<fixed_source>`` element indicates that a fixed source calculation should be
performed. It has the following attributes/sub-elements:
The ``<fixed_source>`` element indicates that a fixed source calculation should
be performed. It has the following attributes/sub-elements:
:batches:
The total number of batches. For fixed source calculations, each batch
@ -296,7 +326,8 @@ out the file and "false" will not.
*Default*: true
.. note:: The tally results will always be written to a binary/HDF5 state point file.
.. note:: The tally results will always be written to a binary/HDF5 state
point file.
``<output_path>`` Element
-------------------------
@ -545,8 +576,8 @@ attributes/sub-elements:
*Default*: None
:separate:
If this element is set to "true", a separate binary source point file will be
written. Otherwise, the source sites will be written in the state point
If this element is set to "true", a separate binary source point file will
be written. Otherwise, the source sites will be written in the state point
directly.
*Default*: false
@ -601,10 +632,56 @@ integers: the batch number, generation number, and particle number.
``<track>`` Element
-------------------
The ``<track>`` element specifies particles for which OpenMC will output binary files describing particle position at every step of its transport. This element should be followed by triplets of integers. Each triplet describes one particle. The integers in each triplet specify the batch number, generation number, and particle number, respectively.
The ``<track>`` element specifies particles for which OpenMC will output binary
files describing particle position at every step of its transport. This element
should be followed by triplets of integers. Each triplet describes one particle
. The integers in each triplet specify the batch number, generation number, and
particle number, respectively.
*Default*: None
.. _trigger:
``<trigger>`` Element
-------------------------
OpenMC includes tally precision triggers which allow the user to define
uncertainty thresholds on :math:`k_{eff}` in the ``<eigenvalue>`` subelement of
``settings.xml``, and/or tallies in ``tallies.xml``. When using triggers,
OpenMC will run until it completes as many batches as defined by ``<batches>``.
At this point, the uncertainties on all tallied values are computed and
compared with their corresponding trigger thresholds. If any triggers have not
been met, OpenMC will continue until either all trigger thresholds have been
satisfied or ``<max_batches>`` has been reached.
The ``<trigger>`` element provides an active "toggle switch" for tally
precision trigger(s), the maximum number of batches and the batch interval. It
has the following attributes/sub-elements:
:active:
This determines whether or not to use trigger(s). Trigger(s) are used when
this tag is set to "true".
:max_batches:
This describes the maximum number of batches allowed when using trigger(s).
.. note:: When max_batches is set, the number of ``batches`` shown in
``<eigenvalue>`` element represents minimum number of batches to
simulate when using the trigger(s).
:batch_interval:
This tag describes the number of batches in between convergence checks.
OpenMC will check if the trigger has been reached at each batch defined
by ``batch_interval`` after the minimum number of batches is reached.
.. note:: If this tag is not present, the ``batch_interval`` is predicted
dynamically by OpenMC for each convergence check. The predictive
model assumes no correlation between fission sources
distributions from batch-to-batch. This assumption is reasonable
for fixed source and small criticality calculations, but is very
optimistic for highly coupled full-core reactor problems.
``<uniform_fs>`` Element
------------------------
@ -1116,6 +1193,8 @@ post-collision energy, and an arbitrary structured mesh.
The three valid elements in the tallies.xml file are ``<tally>``, ``<mesh>``,
and ``<assume_separate>``.
.. _tally:
``<tally>`` Element
-------------------
@ -1139,11 +1218,13 @@ The ``<tally>`` element accepts the following sub-elements:
The ``filter`` element has the following attributes/sub-elements:
:type:
The type of the filter. Accepted options are "cell", "cellborn", "material",
"universe", "energy", "energyout", "mesh", and "distribcell".
The type of the filter. Accepted options are "cell", "cellborn",
"material", "universe", "energy", "energyout", "mesh", and
"distribcell".
:bins:
For each filter type, the corresponding ``bins`` entry is given as follows:
For each filter type, the corresponding ``bins`` entry is given as
follows:
:cell:
A list of cells in which the tally should be accumulated.
@ -1257,20 +1338,20 @@ The ``<tally>`` element accepts the following sub-elements:
:scatter-PN:
Tally all of the scattering moments from order 0 to N, where N is the
Legendre expansion order of the change in particle angle :math:`\left(\mu\right)`.
That is, ``scatter-P1`` is equivalent to requesting tallies of
``scatter-0`` and ``scatter-1``. Like for ``scatter-N``,
N must be between 0 and 10. As an example, tallying up to the
2\ :sup:`nd` \ scattering moment would be specified as
Legendre expansion order of the change in particle angle
:math:`\left(\mu\right)`. That is, ``scatter-P1`` is equivalent to
requesting tallies of ``scatter-0`` and ``scatter-1``. Like for
``scatter-N``, N must be between 0 and 10. As an example, tallying up
to the 2\ :sup:`nd` \ scattering moment would be specified as
``<scores> scatter-P2 </scores>``.
:scatter-YN:
``scatter-YN`` is similar to ``scatter-PN`` except an additional
expansion is performed for the incoming particle direction
:math:`\left(\Omega\right)` using the real spherical harmonics. This is useful
for performing angular flux moment weighting of the scattering moments.
Like ``scatter-PN``, ``scatter-YN`` will tally all of the moments from
order 0 to N; N again must be between 0 and 10.
:math:`\left(\Omega\right)` using the real spherical harmonics. This is
useful for performing angular flux moment weighting of the scattering
moments. Like ``scatter-PN``, ``scatter-YN`` will tally all of the
moments from order 0 to N; N again must be between 0 and 10.
:nu-scatter, nu-scatter-N, nu-scatter-PN, nu-scatter-YN:
These scores are similar in functionality to their ``scatter*``
@ -1300,6 +1381,40 @@ The ``<tally>`` element accepts the following sub-elements:
:events:
Number of scoring events
:trigger:
Precision trigger applied to all filter bins and nuclides for this tally.
It must specify the trigger's type, threshold and scores to which it will
be applied. It has the following attributes/sub-elements:
:type:
The type of the trigger. Accepted options are "variance", "std_dev",
and "rel_err".
:variance:
Variance of the batch mean :math:`\sigma^2`
:std_dev:
Standard deviation of the batch mean :math:`\sigma`
:rel_err:
Relative error of the batch mean :math:`\frac{\sigma}{\mu}`
*Default*: None
:threshold:
The precision trigger's convergence criterion for tallied values.
*Default*: None
:scores:
The score(s) in this tally to which the trigger should be applied.
.. note:: The ``scores`` in ``trigger`` must have been defined in
``scores`` in ``tally``. An optional "all" may be used to
select all scores in this tally.
*Default*: "all"
``<mesh>`` Element
------------------
@ -1338,8 +1453,8 @@ overhead. The effect of assuming all tallies are spatially separate is that once
one tally is scored to, the same event is assumed not to score to any other
tallies. This element should be followed by "true" or "false".
.. warning:: If used incorrectly, the assumption that all tallies are spatially
separate can lead to incorrect results.
.. warning:: If used incorrectly, the assumption that all tallies are
spatially separate can lead to incorrect results.
*Default*: false
@ -1355,8 +1470,10 @@ element of the plots.xml is simply ``<plots>`` and any number output plots can
be defined with ``<plot>`` sub-elements. Two plot types are currently
implemented in openMC:
* ``slice`` 2D pixel plot along one of the major axes. Produces a PPM image file.
* ``voxel`` 3D voxel data dump. Produces a binary file containing voxel xyz position and cell or material id.
* ``slice`` 2D pixel plot along one of the major axes. Produces a PPM image
file.
* ``voxel`` 3D voxel data dump. Produces a binary file containing voxel xyz
position and cell or material id.
``<plot>`` Element
@ -1540,9 +1657,9 @@ attributes or sub-elements. These are not used in "voxel" plots:
CMFD Specification -- cmfd.xml
------------------------------
Coarse mesh finite difference acceleration method has been implemented in OpenMC.
Currently, it allows users to accelerate fission source convergence during
inactive neutron batches. To run CMFD, the ``<run_cmfd>`` element in
Coarse mesh finite difference acceleration method has been implemented in
OpenMC. Currently, it allows users to accelerate fission source convergence
during inactive neutron batches. To run CMFD, the ``<run_cmfd>`` element in
``settings.xml`` should be set to "true".
``<begin>`` Element
@ -1557,8 +1674,8 @@ The ``<begin>`` element controls what batch CMFD calculations should begin.
The ``<display>`` element sets one additional CMFD output column. Options are:
* "balance" - prints the RMS [%] of the resdiual from the neutron balance equation
on CMFD tallies.
* "balance" - prints the RMS [%] of the resdiual from the neutron balance
equation on CMFD tallies.
* "dominance" - prints the estimated dominance ratio from the CMFD iterations.
**This will only work for power iteration eigensolver**.
* "entropy" - prints the *entropy* of the CMFD predicted fission source.
@ -1694,8 +1811,8 @@ not impact the calculation.
``<power_monitor>`` Element
---------------------------
The ``<power_monitor>`` element is used to view the convergence of power iteration.
This option can be turned on with "true" and turned off with "false".
The ``<power_monitor>`` element is used to view the convergence of power
iteration. This option can be turned on with "true" and turned off with "false".
*Default*: false