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Merge branch 'master' into raster3d
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nhorelik
commit
3af332318c
15 changed files with 663 additions and 269 deletions
33
data/readme.rst
Normal file
33
data/readme.rst
Normal file
|
|
@ -0,0 +1,33 @@
|
|||
========================
|
||||
cross_sections.xml Files
|
||||
========================
|
||||
|
||||
As a reminder, in order to run a simulation with OpenMC, you will need cross
|
||||
section data for each nuclide in your problem. OpenMC is not currently
|
||||
distributed with cross section data, so you will have to obtain cross section
|
||||
data by other means. The `user's guide`_ offers some helpful advice on how you
|
||||
can obtain cross sections.
|
||||
|
||||
When OpenMC starts up, it needs a cross_sections.xml file that tells it where to
|
||||
find ACE format cross sections. The files in this directory are configured to
|
||||
work with a few common cross section sources.
|
||||
|
||||
- **cross_sections_ascii.xml** -- This file matches ENDF/B-VII.0 cross sections
|
||||
distributed with MCNP5 / MCNP6 beta.
|
||||
|
||||
- **cross_sections_serpent.xml** -- This file matches ENDF/B-VII.0 cross
|
||||
sections distributed with Serpent 1.1.7.
|
||||
|
||||
- **cross_sections.xml** - This file matches ENDF/B-VII.0 cross sections
|
||||
distributed with MCNP5 / MCNP6 beta *that have been converted to binary*.
|
||||
|
||||
To use any of these files, you need to follow two steps:
|
||||
|
||||
1. Change the path on the ``<directory>`` element in the cross_sections.xml file
|
||||
to the directory containing the ACE files.
|
||||
|
||||
2. Enter the absolute path of the cross_sections.xml on the ``<cross_sections>``
|
||||
element in your settings.xml, or set the CROSS_SECTIONS environment variable to
|
||||
the full path of the cross_sections.xml file.
|
||||
|
||||
.. _user's guide: http://mit-crpg.github.io/openmc/usersguide/install.html#cross-section-configuration
|
||||
|
|
@ -72,6 +72,8 @@ Do not use old-style character/array length (e.g. character*80, real*8).
|
|||
Integer values being used to indicate a certain state should be defined as named
|
||||
constants (see the constants.F90 module for many examples).
|
||||
|
||||
Always use a double colon :: when declaring a variable.
|
||||
|
||||
Yes:
|
||||
|
||||
.. code-block:: fortran
|
||||
|
|
|
|||
|
|
@ -755,7 +755,8 @@ filters can be used for a tally. The following types of filter are available:
|
|||
cell, universe, material, surface, birth region, pre-collision energy,
|
||||
post-collision energy, and an arbitrary structured mesh.
|
||||
|
||||
The two valid elements in the tallies.xml file are ``<tally>`` and ``<mesh>``.
|
||||
The three valid elements in the tallies.xml file are ``<tally>``, ``<mesh>``,
|
||||
and ``<assume_separate>``.
|
||||
|
||||
``<tally>`` Element
|
||||
-------------------
|
||||
|
|
@ -767,12 +768,58 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
for output purposes. This string is limited to 52 characters for formatting
|
||||
purposes.
|
||||
|
||||
:filters:
|
||||
A list of filters to specify what region of phase space should contribute to
|
||||
the tally. See below for full details on what filters are available.
|
||||
:filter:
|
||||
Specify a filter that restricts contributions to the tally to particles
|
||||
within certain regions of phase space. This element and its
|
||||
attributes/sub-elements are described below.
|
||||
|
||||
.. note::
|
||||
You may specify zero, one, or multiple filters to apply to the tally. To
|
||||
specify multiple filters, you must use multiple ``<filter>`` 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", and "mesh".
|
||||
|
||||
:bins:
|
||||
For each filter type, the corresponding ``bins`` entry is given as follows:
|
||||
|
||||
:cell:
|
||||
A list of cells in which the tally should be accumulated.
|
||||
|
||||
:cellborn:
|
||||
This filter allows the tally to be scored to only when particles were
|
||||
originally born in a specified cell.
|
||||
|
||||
:surface:
|
||||
A list of surfaces for which the tally should be accumulated.
|
||||
|
||||
:material:
|
||||
A list of materials for which the tally should be accumulated.
|
||||
|
||||
:universe:
|
||||
A list of universes for which the tally should be accumulated.
|
||||
|
||||
:energy:
|
||||
A monotonically increasing list of bounding **pre-collision** energies
|
||||
for a number of groups. For example, if this filter is specified as
|
||||
``<filter type="energy" bins="0.0 1.0 20.0" />``, then two energy bins
|
||||
will be created, one with energies between 0 and 1 MeV and the other
|
||||
with energies between 1 and 20 MeV.
|
||||
|
||||
:energyout:
|
||||
A monotonically increasing list of bounding **post-collision**
|
||||
energies for a number of groups. For example, if this filter is
|
||||
specified as ``<filter type="energyout" bins="0.0 1.0 20.0" />``, then
|
||||
two post-collision energy bins will be created, one with energies
|
||||
between 0 and 1 MeV and the other with energies between 1 and 20 MeV.
|
||||
|
||||
:mesh:
|
||||
The ``id`` of a structured mesh to be tallied over.
|
||||
|
||||
:nuclides:
|
||||
|
||||
If specified, the scores listed will be for particular nuclides, not the
|
||||
summation of reactions from all nuclides. The format for nuclides should be
|
||||
[Atomic symbol]-[Mass number], e.g. "U-235". The reaction rate for all
|
||||
|
|
@ -787,92 +834,69 @@ The ``<tally>`` element accepts the following sub-elements:
|
|||
*Default*: total
|
||||
|
||||
:scores:
|
||||
The desired responses to be accumulated. See below for full details on the
|
||||
responses which be tallied.
|
||||
A space-separated list of the desired responses to be accumulated. Accepted
|
||||
options are "flux", "total", "scatter", "nu-scatter", "scatter-N",
|
||||
"scatter-PN", "absorption", "fission", "nu-fission", "kappa-fission",
|
||||
"current", and "events". These corresponding to the following physical
|
||||
quantities.
|
||||
|
||||
The following filters can be specified for a tally:
|
||||
:flux:
|
||||
Total flux
|
||||
|
||||
:cell:
|
||||
A list of cells in which the tally should be accumulated.
|
||||
:total:
|
||||
Total reaction rate
|
||||
|
||||
:cellborn:
|
||||
This filter allows the tally to be scored to only when particles were
|
||||
originally born in a specified cell.
|
||||
:scatter:
|
||||
Total scattering rate. Can also be identified with the ``scatter-0``
|
||||
response type.
|
||||
|
||||
:surface:
|
||||
A list of surfaces for which the tally should be accumulated.
|
||||
:nu-scatter:
|
||||
Total production of neutrons due to scattering. This accounts for
|
||||
multiplicity from (n,2n), (n,3n), and (n,4n) reactions and should be
|
||||
slightly higher than the scattering rate.
|
||||
|
||||
:material:
|
||||
A list of materials for which the tally should be accumulated.
|
||||
|
||||
:universe:
|
||||
A list of universes for which the tally should be accumulated.
|
||||
|
||||
:energy:
|
||||
A monotonically increasing list of bounding **pre-collision** energies for a
|
||||
number of groups. For example, if this filter is specified as ``<energy>0.0
|
||||
1.0 20.0</energy>``, then two energy bins will be created, one with energies
|
||||
between 0 and 1 MeV and the other with energies between 1 and 20 MeV.
|
||||
|
||||
:energyout:
|
||||
A monotonically increasing list of bounding **post-collision** energies for
|
||||
a number of groups. For example, if this filter is specified as
|
||||
``<energyout>0.0 1.0 20.0</energyout>``, then two post-collision energy bins
|
||||
will be created, one with energies between 0 and 1 MeV and the other with
|
||||
energies between 1 and 20 MeV.
|
||||
|
||||
:mesh:
|
||||
The ``id`` of a structured mesh to be tallied over.
|
||||
|
||||
The following responses can be tallied.
|
||||
|
||||
:flux:
|
||||
Total flux
|
||||
|
||||
:total:
|
||||
Total reaction rate
|
||||
|
||||
:scatter:
|
||||
Total scattering rate. Can also be identified with the ``scatter-0``
|
||||
response type.
|
||||
|
||||
:nu-scatter:
|
||||
Total production of neutrons due to scattering. This accounts for
|
||||
multiplicity from (n,2n), (n,3n), and (n,4n) reactions and should be
|
||||
slightly higher than the scattering rate.
|
||||
|
||||
:scatter-N:
|
||||
Tally the N\ :sup:`th` \ scattering moment, where N is the Legendre expansion order.
|
||||
N must be between 0 and 10. As an example, tallying the 2\ :sup:`nd` \ scattering
|
||||
moment would be specified as ``<scores> scatter-2 </scores>``.
|
||||
:scatter-N:
|
||||
Tally the N\ :sup:`th` \ scattering moment, where N is the Legendre
|
||||
expansion order. N must be between 0 and 10. As an example, tallying the
|
||||
2\ :sup:`nd` \ scattering moment would be specified as ``<scores>
|
||||
scatter-2 </scores>``.
|
||||
|
||||
:scatter-PN:
|
||||
Tally all of the scattering moments from order 0 to N, where N is
|
||||
the Legendre expansion order. That is, ``scatter-P1`` is equivalent
|
||||
to requesting tallies of ``scatter-0`` and ``scatter-1``.
|
||||
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-PN:
|
||||
Tally all of the scattering moments from order 0 to N, where N is the
|
||||
Legendre expansion order. That is, ``scatter-P1`` is equivalent to
|
||||
requesting tallies of ``scatter-0`` and ``scatter-1``. 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>``.
|
||||
|
||||
:absorption:
|
||||
Total absorption rate. This accounts for all reactions which do not produce
|
||||
secondary neutrons.
|
||||
:absorption:
|
||||
Total absorption rate. This accounts for all reactions which do not
|
||||
produce secondary neutrons.
|
||||
|
||||
:fission:
|
||||
Total fission rate
|
||||
:fission:
|
||||
Total fission rate
|
||||
|
||||
:nu-fission:
|
||||
Total production of neutrons due to fission
|
||||
:nu-fission:
|
||||
Total production of neutrons due to fission
|
||||
|
||||
:kappa-fission:
|
||||
The recoverable energy production rate due to fission. The recoverable
|
||||
energy is defined as the fission product kinetic energy, prompt and delayed neutron
|
||||
kinetic energies, prompt and delayed :math:`\gamma`-ray total energies,
|
||||
and the total energy released by the delayed :math:`\beta` particles. The
|
||||
neutrino energy does not contribute to this response. The prompt and delayed
|
||||
:math:`\gamma`-rays are assumed to deposit their energy locally.
|
||||
:kappa-fission:
|
||||
The recoverable energy production rate due to fission. The recoverable
|
||||
energy is defined as the fission product kinetic energy, prompt and
|
||||
delayed neutron kinetic energies, prompt and delayed :math:`\gamma`-ray
|
||||
total energies, and the total energy released by the delayed :math:`\beta`
|
||||
particles. The neutrino energy does not contribute to this response. The
|
||||
prompt and delayed :math:`\gamma`-rays are assumed to deposit their energy
|
||||
locally.
|
||||
|
||||
:events:
|
||||
Number of scoring events
|
||||
:current:
|
||||
Partial currents on the boundaries of each cell in a mesh.
|
||||
|
||||
.. note::
|
||||
This score can only be used if a mesh filter has been
|
||||
specified. Furthermore, it may not be used in conjunction with any
|
||||
other score.
|
||||
|
||||
:events:
|
||||
Number of scoring events
|
||||
|
||||
``<mesh>`` Element
|
||||
------------------
|
||||
|
|
@ -885,16 +909,24 @@ attributes/sub-elements:
|
|||
The type of structured mesh. Valid options include "rectangular" and
|
||||
"hexagonal".
|
||||
|
||||
:lower_left:
|
||||
The lower-left corner of the structured mesh. If only two coordinate are
|
||||
given, it is assumed that the mesh is an x-y mesh.
|
||||
|
||||
:dimension:
|
||||
The number of mesh cells in each direction.
|
||||
|
||||
:lower_left:
|
||||
The lower-left corner of the structured mesh. If only two coordinates are
|
||||
given, it is assumed that the mesh is an x-y mesh.
|
||||
|
||||
:upper_right:
|
||||
The upper-right corner of the structured mesh. If only two coordinates are
|
||||
given, it is assumed that the mesh is an x-y mesh.
|
||||
|
||||
:width:
|
||||
The width of mesh cells in each direction.
|
||||
|
||||
.. note::
|
||||
One of ``<upper_right>`` or ``<width>`` must be specified, but not both
|
||||
(even if they are consistent with one another).
|
||||
|
||||
``<assume_separate>`` Element
|
||||
-----------------------------
|
||||
|
||||
|
|
@ -902,7 +934,7 @@ In cases where the user needs to specify many different tallies each of which
|
|||
are spatially separate, this tag can be used to cut down on some of the tally
|
||||
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"
|
||||
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.
|
||||
|
|
|
|||
|
|
@ -83,7 +83,7 @@ Prerequisites
|
|||
|
||||
.. _gfortran: http://gcc.gnu.org/wiki/GFortran
|
||||
.. _OpenMPI: http://www.open-mpi.org
|
||||
.. _MPICH2: http://www.mpich.org
|
||||
.. _MPICH: http://www.mpich.org
|
||||
.. _HDF5: http://www.hdfgroup.org/HDF5/
|
||||
.. _PETSc: http://www.mcs.anl.gov/petsc/
|
||||
|
||||
|
|
|
|||
|
|
@ -11,8 +11,8 @@ Problems with Compilation
|
|||
If you are experiencing problems trying to compile OpenMC, first check if the
|
||||
error you are receiving is among the following options.
|
||||
|
||||
undefined reference to `_vtab$...
|
||||
*********************************
|
||||
undefined reference to \`_vtab$...
|
||||
**********************************
|
||||
|
||||
If you see this message when trying to compile, the most likely cause is that
|
||||
you are using a compiler that does not support type-bound procedures from
|
||||
|
|
|
|||
12
readme.rst
12
readme.rst
|
|
@ -8,9 +8,9 @@ continuous-energy transport code that uses ACE format cross sections. The
|
|||
project started under the Computational Reactor Physics Group at MIT.
|
||||
|
||||
Complete documentation on the usage of OpenMC is hosted on GitHub at
|
||||
http://mit-crpg.github.com/openmc/. If you are interested in the project or
|
||||
would like to help and contribute, please send a message to the OpenMC User's
|
||||
Group `mailing list`_.
|
||||
http://mit-crpg.github.io/openmc/. If you are interested in the project or would
|
||||
like to help and contribute, please send a message to the OpenMC User's Group
|
||||
`mailing list`_.
|
||||
|
||||
------------
|
||||
Installation
|
||||
|
|
@ -46,7 +46,7 @@ License
|
|||
OpenMC is distributed under the MIT/X license_.
|
||||
|
||||
.. _mailing list: https://groups.google.com/forum/?fromgroups=#!forum/openmc-users
|
||||
.. _installation instructions: http://mit-crpg.github.com/openmc/usersguide/install.html
|
||||
.. _Troubleshooting section: http://mit-crpg.github.com/openmc/usersguide/troubleshoot.html
|
||||
.. _installation instructions: http://mit-crpg.github.io/openmc/usersguide/install.html
|
||||
.. _Troubleshooting section: http://mit-crpg.github.io/openmc/usersguide/troubleshoot.html
|
||||
.. _Issues: https://github.com/mit-crpg/openmc/issues
|
||||
.. _license: http://mit-crpg.github.com/openmc/license.html
|
||||
.. _license: http://mit-crpg.github.io/openmc/license.html
|
||||
|
|
|
|||
|
|
@ -332,15 +332,14 @@ source.o: output.o
|
|||
source.o: particle_header.o
|
||||
source.o: physics.o
|
||||
source.o: random_lcg.o
|
||||
source.o: state_point.o
|
||||
source.o: string.o
|
||||
|
||||
state_point.o: error.o
|
||||
state_point.o: global.o
|
||||
state_point.o: math.o
|
||||
state_point.o: output.o
|
||||
state_point.o: source.o
|
||||
state_point.o: string.o
|
||||
state_point.o: tally.o
|
||||
state_point.o: tally_header.o
|
||||
|
||||
string.o: constants.o
|
||||
|
|
|
|||
|
|
@ -1195,6 +1195,7 @@ contains
|
|||
dims(1) = restart_batch
|
||||
call h5ltread_dataset_double_f(hdf5_state_point, "k_batch", &
|
||||
k_batch(1:restart_batch), dims, hdf5_err)
|
||||
dims(1) = restart_batch*gen_per_batch
|
||||
call h5ltread_dataset_double_f(hdf5_state_point, "entropy", &
|
||||
entropy(1:restart_batch*gen_per_batch), dims, hdf5_err)
|
||||
call hdf5_read_double(hdf5_state_point, "k_col_abs", k_col_abs)
|
||||
|
|
|
|||
172
src/source.F90
172
src/source.F90
|
|
@ -9,6 +9,7 @@ module source
|
|||
use particle_header, only: deallocate_coord
|
||||
use physics, only: maxwell_spectrum, watt_spectrum
|
||||
use random_lcg, only: prn, set_particle_seed
|
||||
use state_point, only: read_source_binary
|
||||
use string, only: to_str
|
||||
|
||||
#ifdef MPI
|
||||
|
|
@ -229,175 +230,4 @@ contains
|
|||
|
||||
end subroutine initialize_particle
|
||||
|
||||
!===============================================================================
|
||||
! WRITE_SOURCE writes out the final source distribution to a binary file that
|
||||
! can be used as a starting source in a new simulation
|
||||
!===============================================================================
|
||||
|
||||
subroutine write_source_binary()
|
||||
|
||||
#ifdef MPI
|
||||
integer :: fh ! file handle
|
||||
integer(MPI_OFFSET_KIND) :: offset ! offset in memory (0=beginning of file)
|
||||
|
||||
! ==========================================================================
|
||||
! PARALLEL I/O USING MPI-2 ROUTINES
|
||||
|
||||
! Open binary source file for reading
|
||||
call MPI_FILE_OPEN(MPI_COMM_WORLD, path_source, MPI_MODE_CREATE + &
|
||||
MPI_MODE_WRONLY, MPI_INFO_NULL, fh, mpi_err)
|
||||
|
||||
if (master) then
|
||||
offset = 0
|
||||
call MPI_FILE_WRITE_AT(fh, offset, n_particles, 1, MPI_INTEGER8, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
end if
|
||||
|
||||
! Set proper offset for source data on this processor
|
||||
offset = 8*(1 + rank*maxwork*8)
|
||||
|
||||
! Write all source sites
|
||||
call MPI_FILE_WRITE_AT(fh, offset, source_bank(1), work, MPI_BANK, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
! Close binary source file
|
||||
call MPI_FILE_CLOSE(fh, mpi_err)
|
||||
|
||||
#else
|
||||
! ==========================================================================
|
||||
! SERIAL I/O USING FORTRAN INTRINSIC ROUTINES
|
||||
|
||||
! Open binary source file for writing
|
||||
open(UNIT=UNIT_SOURCE, FILE=path_source, STATUS='replace', &
|
||||
ACCESS='stream')
|
||||
|
||||
! Write the number of particles
|
||||
write(UNIT=UNIT_SOURCE) n_particles
|
||||
|
||||
! Write information from the source bank
|
||||
write(UNIT=UNIT_SOURCE) source_bank(1:work)
|
||||
|
||||
! Close binary source file
|
||||
close(UNIT=UNIT_SOURCE)
|
||||
#endif
|
||||
|
||||
end subroutine write_source_binary
|
||||
|
||||
!===============================================================================
|
||||
! READ_SOURCE_BINARY reads a source distribution from a source.binary file and
|
||||
! initializes the source bank
|
||||
!===============================================================================
|
||||
|
||||
subroutine read_source_binary()
|
||||
|
||||
integer :: i ! loop over repeating sites
|
||||
integer(8) :: n_sites ! number of sites in binary file
|
||||
integer :: n_repeat ! number of times to repeat a site
|
||||
#ifdef MPI
|
||||
integer :: fh ! file handle
|
||||
integer(MPI_OFFSET_KIND) :: offset ! offset in memory (0=beginning of file)
|
||||
integer :: n_read ! number of sites to read on a single process
|
||||
#endif
|
||||
|
||||
#ifdef MPI
|
||||
! ==========================================================================
|
||||
! PARALLEL I/O USING MPI-2 ROUTINES
|
||||
|
||||
! Open binary source file for reading
|
||||
call MPI_FILE_OPEN(MPI_COMM_WORLD, path_source, MPI_MODE_RDONLY, &
|
||||
MPI_INFO_NULL, fh, mpi_err)
|
||||
|
||||
! Read number of source sites in file
|
||||
offset = 0
|
||||
call MPI_FILE_READ_AT(fh, offset, n_sites, 1, MPI_INTEGER8, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
if (n_particles > n_sites) then
|
||||
! Determine number of sites to read and offset
|
||||
if (rank <= mod(n_sites,int(n_procs,8)) - 1) then
|
||||
n_read = int(n_sites/n_procs) + 1
|
||||
offset = 8*(1 + rank*n_read*8)
|
||||
else
|
||||
n_read = int(n_sites/n_procs)
|
||||
offset = 8*(1 + (rank*n_read + mod(n_sites,int(n_procs,8)))*8)
|
||||
end if
|
||||
|
||||
! Read source sites
|
||||
call MPI_FILE_READ_AT(fh, offset, source_bank(1), n_read, MPI_BANK, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
! Let's say we have 30 sites and we need to fill in 200. This do loop
|
||||
! will fill in sites 31 - 180.
|
||||
|
||||
n_repeat = int(work / n_read)
|
||||
do i = 1, n_repeat - 1
|
||||
source_bank(i*n_read + 1:(i+1)*n_read) = &
|
||||
source_bank((i-1)*n_read + 1:i*n_read)
|
||||
end do
|
||||
|
||||
! This final statement would fill sites 181 - 200 in the above example.
|
||||
|
||||
if (mod(work, int(n_repeat*n_read,8)) > 0) then
|
||||
source_bank(n_repeat*n_read + 1:work) = &
|
||||
source_bank(1:work - n_repeat * n_read)
|
||||
end if
|
||||
|
||||
else
|
||||
! Set proper offset for source data on this processor
|
||||
offset = 8*(1 + rank*maxwork*8)
|
||||
|
||||
! Read all source sites
|
||||
call MPI_FILE_READ_AT(fh, offset, source_bank(1), work, MPI_BANK, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
! Close binary source file
|
||||
call MPI_FILE_CLOSE(fh, mpi_err)
|
||||
end if
|
||||
|
||||
#else
|
||||
! ==========================================================================
|
||||
! SERIAL I/O USING FORTRAN INTRINSIC ROUTINES
|
||||
|
||||
! Open binary source file for reading
|
||||
open(UNIT=UNIT_SOURCE, FILE=path_source, STATUS='old', &
|
||||
ACCESS='stream')
|
||||
|
||||
! Read number of source sites in file
|
||||
read(UNIT=UNIT_SOURCE) n_sites
|
||||
|
||||
if (n_particles > n_sites) then
|
||||
! The size of the source file is smaller than the number of particles we
|
||||
! need. Thus, read all sites and then duplicate sites as necessary.
|
||||
|
||||
read(UNIT=UNIT_SOURCE) source_bank(1:n_sites)
|
||||
|
||||
! Let's say we have 300 sites and we need to fill in 1000. This do loop
|
||||
! will fill in sites 301 - 900.
|
||||
|
||||
n_repeat = int(n_particles / n_sites)
|
||||
do i = 1, n_repeat - 1
|
||||
source_bank(i*n_sites + 1:(i+1)*n_sites) = &
|
||||
source_bank((i-1)*n_sites + 1:i*n_sites)
|
||||
end do
|
||||
|
||||
! This final statement would fill sites 901 - 1000 in the above example.
|
||||
|
||||
source_bank(n_repeat*n_sites + 1:n_particles) = &
|
||||
source_bank(1:n_particles - n_repeat * n_sites)
|
||||
|
||||
else
|
||||
! The size of the source file is bigger than or equal to the number of
|
||||
! particles we need for one generation. Thus, we can just read as many
|
||||
! sites as we need.
|
||||
|
||||
read(UNIT=UNIT_SOURCE) source_bank(1:n_particles)
|
||||
|
||||
end if
|
||||
|
||||
! Close binary source file
|
||||
close(UNIT=UNIT_SOURCE)
|
||||
#endif
|
||||
|
||||
end subroutine read_source_binary
|
||||
|
||||
end module source
|
||||
|
|
|
|||
|
|
@ -22,10 +22,8 @@ module state_point
|
|||
use global
|
||||
use math, only: t_percentile
|
||||
use output, only: write_message, print_batch_keff, time_stamp
|
||||
use source, only: write_source_binary
|
||||
use string, only: to_str
|
||||
use tally_header, only: TallyObject
|
||||
use tally, only: setup_active_usertallies
|
||||
|
||||
#ifdef MPI
|
||||
use mpi
|
||||
|
|
@ -1113,4 +1111,175 @@ contains
|
|||
|
||||
end subroutine replay_batch_history
|
||||
|
||||
!===============================================================================
|
||||
! WRITE_SOURCE writes out the final source distribution to a binary file that
|
||||
! can be used as a starting source in a new simulation
|
||||
!===============================================================================
|
||||
|
||||
subroutine write_source_binary()
|
||||
|
||||
#ifdef MPI
|
||||
integer :: fh ! file handle
|
||||
integer(MPI_OFFSET_KIND) :: offset ! offset in memory (0=beginning of file)
|
||||
|
||||
! ==========================================================================
|
||||
! PARALLEL I/O USING MPI-2 ROUTINES
|
||||
|
||||
! Open binary source file for reading
|
||||
call MPI_FILE_OPEN(MPI_COMM_WORLD, path_source, MPI_MODE_CREATE + &
|
||||
MPI_MODE_WRONLY, MPI_INFO_NULL, fh, mpi_err)
|
||||
|
||||
if (master) then
|
||||
offset = 0
|
||||
call MPI_FILE_WRITE_AT(fh, offset, n_particles, 1, MPI_INTEGER8, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
end if
|
||||
|
||||
! Set proper offset for source data on this processor
|
||||
offset = 8*(1 + rank*maxwork*8)
|
||||
|
||||
! Write all source sites
|
||||
call MPI_FILE_WRITE_AT(fh, offset, source_bank(1), work, MPI_BANK, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
! Close binary source file
|
||||
call MPI_FILE_CLOSE(fh, mpi_err)
|
||||
|
||||
#else
|
||||
! ==========================================================================
|
||||
! SERIAL I/O USING FORTRAN INTRINSIC ROUTINES
|
||||
|
||||
! Open binary source file for writing
|
||||
open(UNIT=UNIT_SOURCE, FILE=path_source, STATUS='replace', &
|
||||
ACCESS='stream')
|
||||
|
||||
! Write the number of particles
|
||||
write(UNIT=UNIT_SOURCE) n_particles
|
||||
|
||||
! Write information from the source bank
|
||||
write(UNIT=UNIT_SOURCE) source_bank(1:work)
|
||||
|
||||
! Close binary source file
|
||||
close(UNIT=UNIT_SOURCE)
|
||||
#endif
|
||||
|
||||
end subroutine write_source_binary
|
||||
|
||||
!===============================================================================
|
||||
! READ_SOURCE_BINARY reads a source distribution from a source.binary file and
|
||||
! initializes the source bank
|
||||
!===============================================================================
|
||||
|
||||
subroutine read_source_binary()
|
||||
|
||||
integer :: i ! loop over repeating sites
|
||||
integer(8) :: n_sites ! number of sites in binary file
|
||||
integer :: n_repeat ! number of times to repeat a site
|
||||
#ifdef MPI
|
||||
integer :: fh ! file handle
|
||||
integer(MPI_OFFSET_KIND) :: offset ! offset in memory (0=beginning of file)
|
||||
integer :: n_read ! number of sites to read on a single process
|
||||
#endif
|
||||
|
||||
#ifdef MPI
|
||||
! ==========================================================================
|
||||
! PARALLEL I/O USING MPI-2 ROUTINES
|
||||
|
||||
! Open binary source file for reading
|
||||
call MPI_FILE_OPEN(MPI_COMM_WORLD, path_source, MPI_MODE_RDONLY, &
|
||||
MPI_INFO_NULL, fh, mpi_err)
|
||||
|
||||
! Read number of source sites in file
|
||||
offset = 0
|
||||
call MPI_FILE_READ_AT(fh, offset, n_sites, 1, MPI_INTEGER8, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
if (n_particles > n_sites) then
|
||||
! Determine number of sites to read and offset
|
||||
if (rank <= mod(n_sites,int(n_procs,8)) - 1) then
|
||||
n_read = int(n_sites/n_procs) + 1
|
||||
offset = 8*(1 + rank*n_read*8)
|
||||
else
|
||||
n_read = int(n_sites/n_procs)
|
||||
offset = 8*(1 + (rank*n_read + mod(n_sites,int(n_procs,8)))*8)
|
||||
end if
|
||||
|
||||
! Read source sites
|
||||
call MPI_FILE_READ_AT(fh, offset, source_bank(1), n_read, MPI_BANK, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
! Let's say we have 30 sites and we need to fill in 200. This do loop
|
||||
! will fill in sites 31 - 180.
|
||||
|
||||
n_repeat = int(work / n_read)
|
||||
do i = 1, n_repeat - 1
|
||||
source_bank(i*n_read + 1:(i+1)*n_read) = &
|
||||
source_bank((i-1)*n_read + 1:i*n_read)
|
||||
end do
|
||||
|
||||
! This final statement would fill sites 181 - 200 in the above example.
|
||||
|
||||
if (mod(work, int(n_repeat*n_read,8)) > 0) then
|
||||
source_bank(n_repeat*n_read + 1:work) = &
|
||||
source_bank(1:work - n_repeat * n_read)
|
||||
end if
|
||||
|
||||
else
|
||||
! Set proper offset for source data on this processor
|
||||
offset = 8*(1 + rank*maxwork*8)
|
||||
|
||||
! Read all source sites
|
||||
call MPI_FILE_READ_AT(fh, offset, source_bank(1), work, MPI_BANK, &
|
||||
MPI_STATUS_IGNORE, mpi_err)
|
||||
|
||||
! Close binary source file
|
||||
call MPI_FILE_CLOSE(fh, mpi_err)
|
||||
end if
|
||||
|
||||
#else
|
||||
! ==========================================================================
|
||||
! SERIAL I/O USING FORTRAN INTRINSIC ROUTINES
|
||||
|
||||
! Open binary source file for reading
|
||||
open(UNIT=UNIT_SOURCE, FILE=path_source, STATUS='old', &
|
||||
ACCESS='stream')
|
||||
|
||||
! Read number of source sites in file
|
||||
read(UNIT=UNIT_SOURCE) n_sites
|
||||
|
||||
if (n_particles > n_sites) then
|
||||
! The size of the source file is smaller than the number of particles we
|
||||
! need. Thus, read all sites and then duplicate sites as necessary.
|
||||
|
||||
read(UNIT=UNIT_SOURCE) source_bank(1:n_sites)
|
||||
|
||||
! Let's say we have 300 sites and we need to fill in 1000. This do loop
|
||||
! will fill in sites 301 - 900.
|
||||
|
||||
n_repeat = int(n_particles / n_sites)
|
||||
do i = 1, n_repeat - 1
|
||||
source_bank(i*n_sites + 1:(i+1)*n_sites) = &
|
||||
source_bank((i-1)*n_sites + 1:i*n_sites)
|
||||
end do
|
||||
|
||||
! This final statement would fill sites 901 - 1000 in the above example.
|
||||
|
||||
source_bank(n_repeat*n_sites + 1:n_particles) = &
|
||||
source_bank(1:n_particles - n_repeat * n_sites)
|
||||
|
||||
else
|
||||
! The size of the source file is bigger than or equal to the number of
|
||||
! particles we need for one generation. Thus, we can just read as many
|
||||
! sites as we need.
|
||||
|
||||
read(UNIT=UNIT_SOURCE) source_bank(1:n_particles)
|
||||
|
||||
end if
|
||||
|
||||
! Close binary source file
|
||||
close(UNIT=UNIT_SOURCE)
|
||||
#endif
|
||||
|
||||
end subroutine read_source_binary
|
||||
|
||||
end module state_point
|
||||
|
|
|
|||
296
src/utils/plot_mesh_tally.py
Executable file
296
src/utils/plot_mesh_tally.py
Executable file
|
|
@ -0,0 +1,296 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
'''Python script to plot tally data generated by OpenMC.'''
|
||||
|
||||
import sys
|
||||
from statepoint import *
|
||||
|
||||
# Color intensity dependent on individual score?
|
||||
|
||||
from PyQt4.QtCore import *
|
||||
from PyQt4.QtGui import *
|
||||
import matplotlib.pyplot as plt
|
||||
from matplotlib.figure import Figure
|
||||
from matplotlib.backends.backend_qt4agg import FigureCanvasQTAgg as FigureCanvas
|
||||
from matplotlib.backends.backend_qt4agg import NavigationToolbar2QTAgg as NavigationToolbar
|
||||
import numpy as np
|
||||
|
||||
class AppForm(QMainWindow):
|
||||
def __init__(self, parent=None):
|
||||
QMainWindow.__init__(self, parent)
|
||||
|
||||
# Read data from source or leakage fraction file
|
||||
self.get_file_data()
|
||||
self.main_frame = QWidget()
|
||||
self.setCentralWidget(self.main_frame)
|
||||
|
||||
# Create the Figure, Canvas, and Axes
|
||||
self.dpi = 100
|
||||
self.fig = Figure((5.0, 15.0), dpi=self.dpi)
|
||||
self.canvas = FigureCanvas(self.fig)
|
||||
self.canvas.setParent(self.main_frame)
|
||||
self.axes = self.fig.add_subplot(111)
|
||||
|
||||
# Create the navigation toolbar, tied to the canvas
|
||||
self.mpl_toolbar = NavigationToolbar(self.canvas, self.main_frame)
|
||||
|
||||
# Grid layout at bottom
|
||||
self.grid = QGridLayout()
|
||||
|
||||
# Overall layout
|
||||
self.vbox = QVBoxLayout()
|
||||
self.vbox.addWidget(self.canvas)
|
||||
self.vbox.addWidget(self.mpl_toolbar)
|
||||
self.vbox.addLayout(self.grid)
|
||||
self.main_frame.setLayout(self.vbox)
|
||||
|
||||
# Tally selections
|
||||
label_tally = QLabel("Tally:")
|
||||
self.tally = QComboBox()
|
||||
self.tally.addItems([(str(i + 1)) for i in range(self.n_tallies)])
|
||||
self.connect(self.tally, SIGNAL('activated(int)'),
|
||||
self._update)
|
||||
self.connect(self.tally, SIGNAL('activated(int)'),
|
||||
self.populate_boxes)
|
||||
self.connect(self.tally, SIGNAL('activated(int)'),
|
||||
self.on_draw)
|
||||
|
||||
# Planar basis
|
||||
label_basis = QLabel("Basis:")
|
||||
self.basis = QComboBox()
|
||||
self.basis.addItems(['xy', 'yz', 'xz'])
|
||||
|
||||
# Update window when 'Basis' selection is changed
|
||||
self.connect(self.basis, SIGNAL('activated(int)'),
|
||||
self._update)
|
||||
self.connect(self.basis, SIGNAL('activated(int)'),
|
||||
self.populate_boxes)
|
||||
self.connect(self.basis, SIGNAL('activated(int)'),
|
||||
self.on_draw)
|
||||
|
||||
# Axial level within selected basis
|
||||
label_axial_level = QLabel("Axial Level:")
|
||||
self.axial_level = QComboBox()
|
||||
self.connect(self.axial_level, SIGNAL('activated(int)'),
|
||||
self.on_draw)
|
||||
|
||||
self.label_filters = QLabel("Filter options:")
|
||||
|
||||
# Labels for all possible filters
|
||||
self.labels = {'cell': 'Cell: ', 'cellborn': 'Cell born: ',
|
||||
'surface': 'Surface: ', 'material': 'Material',
|
||||
'universe': 'Universe: ', 'energyin': 'Energy in: ',
|
||||
'energyout': 'Energy out: '}
|
||||
|
||||
# Empty reusable labels
|
||||
self.qlabels = {}
|
||||
for j in range(8):
|
||||
self.nextLabel = QLabel
|
||||
self.qlabels[j] = self.nextLabel
|
||||
|
||||
# Reusable comboboxes labelled with filter names
|
||||
self.boxes = {}
|
||||
for key in self.labels.keys():
|
||||
self.nextBox = QComboBox()
|
||||
self.connect(self.nextBox, SIGNAL('activated(int)'),
|
||||
self.on_draw)
|
||||
self.boxes[key] = self.nextBox
|
||||
|
||||
# Combobox to select among scores
|
||||
self.score_label = QLabel("Score:")
|
||||
self.scoreBox = QComboBox()
|
||||
for item in self.tally_scores[0]:
|
||||
self.scoreBox.addItems(str(item))
|
||||
self.connect(self.scoreBox, SIGNAL('activated(int)'),
|
||||
self.on_draw)
|
||||
|
||||
# Fill layout
|
||||
self.grid.addWidget(label_tally, 0, 0)
|
||||
self.grid.addWidget(self.tally, 0, 1)
|
||||
self.grid.addWidget(label_basis, 1, 0)
|
||||
self.grid.addWidget(self.basis, 1, 1)
|
||||
self.grid.addWidget(label_axial_level, 2, 0)
|
||||
self.grid.addWidget(self.axial_level, 2, 1)
|
||||
self.grid.addWidget(self.label_filters, 3, 0)
|
||||
|
||||
self._update()
|
||||
self.populate_boxes()
|
||||
self.on_draw()
|
||||
|
||||
def get_file_data(self):
|
||||
# Get data file name from "open file" browser
|
||||
filename = QFileDialog.getOpenFileName(self, 'Select statepoint file', '.')
|
||||
|
||||
# Create StatePoint object and read in data
|
||||
self.datafile = StatePoint(str(filename))
|
||||
self.datafile.read_results()
|
||||
self.datafile.generate_stdev()
|
||||
|
||||
self.setWindowTitle('Core Map Tool : ' + str(self.datafile.path))
|
||||
|
||||
# Set maximum colorbar value by maximum tally data value
|
||||
self.maxvalue = self.datafile.tallies[0].results.max()
|
||||
|
||||
self.labelList = []
|
||||
|
||||
# Read mesh dimensions
|
||||
# for mesh in self.datafile.meshes:
|
||||
# self.nx, self.ny, self.nz = mesh.dimension
|
||||
|
||||
# Read filter types from statepoint file
|
||||
self.n_tallies = len(self.datafile.tallies)
|
||||
self.tally_list = []
|
||||
for tally in self.datafile.tallies:
|
||||
self.filter_types = []
|
||||
for f in tally.filters:
|
||||
self.filter_types.append(f)
|
||||
self.tally_list.append(self.filter_types)
|
||||
|
||||
# Read score types from statepoint file
|
||||
self.tally_scores = []
|
||||
for tally in self.datafile.tallies:
|
||||
self.score_types = []
|
||||
for s in tally.scores:
|
||||
self.score_types.append(s)
|
||||
self.tally_scores.append(self.score_types)
|
||||
# print 'self.tally_scores = ', self.tally_scores
|
||||
|
||||
def on_draw(self):
|
||||
""" Redraws the figure
|
||||
"""
|
||||
|
||||
# print 'Calling on_draw...'
|
||||
# Get selected basis, axial_level and stage
|
||||
basis = self.basis.currentIndex() + 1
|
||||
axial_level = self.axial_level.currentIndex() + 1
|
||||
|
||||
# Create spec_list
|
||||
spec_list = []
|
||||
for tally in self.datafile.tallies[self.tally.currentIndex()].filters.values():
|
||||
if tally.type == 'mesh':
|
||||
continue
|
||||
index = self.boxes[tally.type].currentIndex()
|
||||
spec_list.append((tally.type, index))
|
||||
|
||||
if self.basis.currentText() == 'xy':
|
||||
matrix = np.zeros((self.nx, self.ny))
|
||||
for i in range(self.nx):
|
||||
for j in range(self.ny):
|
||||
matrix[i,j] = self.datafile.get_value(self.tally.currentIndex(), spec_list + [('mesh', (i, j, axial_level))], self.scoreBox.currentIndex())[0]
|
||||
|
||||
elif self.basis.currentText() == 'yz':
|
||||
matrix = np.zeros((self.ny, self.nz))
|
||||
for i in range(self.ny):
|
||||
for j in range(self.nz):
|
||||
matrix[i,j] = self.datafile.get_value(self.tally.currentIndex(), spec_list + [('mesh', (axial_level, i, j))], self.scoreBox.currentIndex())[0]
|
||||
|
||||
else:
|
||||
matrix = np.zeros((self.nx, self.nz))
|
||||
for i in range(self.nx):
|
||||
for j in range(self.nz):
|
||||
matrix[i,j] = self.datafile.get_value(self.tally.currentIndex(), spec_list + [('mesh', (i, axial_level, j))], self.scoreBox.currentIndex())[0]
|
||||
|
||||
# print spec_list
|
||||
|
||||
# Clear the figure
|
||||
self.fig.clear()
|
||||
|
||||
# Make figure, set up color bar
|
||||
self.axes = self.fig.add_subplot(111)
|
||||
cax = self.axes.imshow(matrix, vmin=0.0, vmax=matrix.max(), interpolation="nearest")
|
||||
self.fig.colorbar(cax)
|
||||
|
||||
self.axes.set_xticks([])
|
||||
self.axes.set_yticks([])
|
||||
self.axes.set_aspect('equal')
|
||||
|
||||
# Draw canvas
|
||||
self.canvas.draw()
|
||||
|
||||
def _update(self):
|
||||
'''Updates widget to display new relevant comboboxes and figure data
|
||||
'''
|
||||
# print 'Calling _update...'
|
||||
|
||||
self.mesh = self.datafile.meshes[self.datafile.tallies[self.tally.currentIndex()].filters['mesh'].bins[0] - 1]
|
||||
|
||||
self.nx, self.ny, self.nz = self.mesh.dimension
|
||||
|
||||
# Clear axial level combobox
|
||||
self.axial_level.clear()
|
||||
|
||||
# Repopulate axial level combobox based on current basis selection
|
||||
if (self.basis.currentText() == 'xy'):
|
||||
self.axial_level.addItems([str(i+1) for i in range(self.nz)])
|
||||
elif (self.basis.currentText() == 'yz'):
|
||||
self.axial_level.addItems([str(i+1) for i in range(self.nx)])
|
||||
else:
|
||||
self.axial_level.addItems([str(i+1) for i in range(self.ny)])
|
||||
|
||||
# Determine maximum value from current tally data set
|
||||
self.maxvalue = self.datafile.tallies[self.tally.currentIndex()].results.max()
|
||||
# print self.maxvalue
|
||||
|
||||
# Clear and hide old filter labels
|
||||
for item in self.labelList:
|
||||
item.clear()
|
||||
|
||||
# Clear and hide old filter boxes
|
||||
for j in self.labels:
|
||||
self.boxes[j].clear()
|
||||
self.boxes[j].setParent(None)
|
||||
|
||||
self.update()
|
||||
|
||||
def populate_boxes(self):
|
||||
# print 'Calling populate_boxes...'
|
||||
|
||||
n = 4
|
||||
labels = {'cell': 'Cell : ',
|
||||
'cellborn': 'Cell born: ',
|
||||
'surface': 'Surface: ',
|
||||
'material': 'Material: ',
|
||||
'universe': 'Universe: '}
|
||||
|
||||
# For each filter in newly-selected tally, name a label and fill the
|
||||
# relevant combobox with options
|
||||
for element in self.tally_list[self.tally.currentIndex()]:
|
||||
nextFilter = self.datafile.tallies[self.tally.currentIndex()].filters[element]
|
||||
if element == 'mesh':
|
||||
continue
|
||||
|
||||
label = QLabel(self.labels[element])
|
||||
self.labelList.append(label)
|
||||
combobox = self.boxes[element]
|
||||
self.grid.addWidget(label, n, 0)
|
||||
self.grid.addWidget(combobox, n, 1)
|
||||
n += 1
|
||||
|
||||
# print element
|
||||
if element in ['cell', 'cellborn', 'surface', 'material', 'universe']:
|
||||
combobox.addItems([str(i) for i in nextFilter.bins])
|
||||
# for i in nextFilter.bins:
|
||||
# print i
|
||||
|
||||
elif element == 'energyin' or element == 'energyout':
|
||||
for i in range(nextFilter.length):
|
||||
text = str(nextFilter.bins[i]) + ' to ' + str(nextFilter.bins[i+1])
|
||||
combobox.addItem(text)
|
||||
|
||||
self.scoreBox.clear()
|
||||
for item in self.tally_scores[self.tally.currentIndex()]:
|
||||
self.scoreBox.addItem(str(item))
|
||||
self.grid.addWidget(self.score_label, n, 0)
|
||||
self.grid.addWidget(self.scoreBox, n, 1)
|
||||
|
||||
|
||||
|
||||
def main():
|
||||
app = QApplication(sys.argv)
|
||||
form = AppForm()
|
||||
form.show()
|
||||
app.exec_()
|
||||
|
||||
|
||||
if __name__ == "__main__":
|
||||
main()
|
||||
32
tests/readme.rst
Normal file
32
tests/readme.rst
Normal file
|
|
@ -0,0 +1,32 @@
|
|||
=================
|
||||
OpenMC Test Suite
|
||||
=================
|
||||
|
||||
The purpose of this test suite is to ensure that OpenMC compiles using various
|
||||
combinations of compiler flags and options and that all user input options can
|
||||
be used successfully without breaking the code. The test suite is by no means
|
||||
complete and should not be viewed as a comprehensive unit test suite will full
|
||||
coverage. Until more effort can be put into actual unit testing, this suite is a
|
||||
simple means of making sure that new features added into the code don't break
|
||||
existing features.
|
||||
|
||||
The test suite is designed to run with the third-party Python package
|
||||
nose_. Running the test suite is as simple as going to the tests/ directory and
|
||||
running:
|
||||
|
||||
.. sh::
|
||||
nosetests
|
||||
|
||||
However, usually testing is split into two parts: compilation and running. To
|
||||
run the compilation tests, use:
|
||||
|
||||
.. sh::
|
||||
nosetests test_compile
|
||||
|
||||
Then, to run all the normal tests (which require that an OpenMC executable is
|
||||
already built):
|
||||
|
||||
.. sh::
|
||||
nosetests --exclude-dir=test_compile
|
||||
|
||||
.. _nose: https://nose.readthedocs.org
|
||||
Loading…
Add table
Add a link
Reference in a new issue