.. _usersguide_processing: ================================= Data Processing and Visualization ================================= This section is intended to explain in detail the recommended procedures for carrying out common post-processing tasks with OpenMC. While several utilities of varying complexity are provided to help automate the process, in many cases it will be extremely beneficial to do some coding in Python to quickly obtain results. In these cases, and for many of the provided utilities, it is necessary for your Python installation to contain: * [1]_ `Numpy `_ * [1]_ `Scipy `_ * [2]_ `h5py `_ * [3]_ `Matplotlib `_ * [3]_ `Silomesh `_ * [3]_ `VTK `_ * [4]_ `PyQt `_ Most of these are easily obtainable in Ubuntu through the package manager, or are easily installed with distutils. .. [1] Required for tally data extraction from statepoints with statepoint.py .. [2] Required only if reading HDF5 statepoint files. .. [3] Optional for plotting utilities .. [4] Optional for interactive GUIs ---------------------- Geometry Visualization ---------------------- Geometry plotting is carried out by creating a plots.xml, specifying plots, and running OpenMC with the -plot or -p command-line option (See :ref:`usersguide_plotting`). Plotting in 2D -------------- .. image:: ../_images/atr.png :height: 200px See below for a simple example of a plots xml file that demonstrates the capabilities of 2D slice plots. Here we assume that there is a ``geometry.xml`` file containing 7 cells. .. code-block:: xml myplot 0 0 10 10 2000 2000 0 0 0 1 3 4 5 6 In this example, OpenMC will produce a plot named ``myplot.ppm`` when run in plotting mode. The picture will be on the xy-plane, depicting the rectangle between points (-5,-5) and (5,5) with 2000 pixels along each dimension. The color of each pixel is determined by placing a particle at the center of that pixel and using OpenMC's internal ``find_cell`` routine (the same one used for particle tracking during simulation) to determine the cell and material at that location. In this example, pixels are 10/2000=0.005 cm wide, so points will be at (-4.9975,-4.9975), (-4.9950,-4.9975), (-4.9925,-4.9975), etc. This is pointed out to demonstrate that this plot may miss any features smaller than 0.005 cm, since they could exist between pixel centers. More pixels can be used to resolve finer features, but could result in larger files. The ``background``, ``col_spec``, and ``mask`` elements define how to set pixel colors based on the cell ids at each pixel center. In this example, RGB colors are specified for cells 1,2,3,4, and 7, a random color will be assigned to cells 5 and 6, and a black background color (``rgb="0 0 0"``) will be applied to locations where no cell is defined. However, the ``mask`` element here says that only cells 1,3,4,5, and 6 should be displayed, with other cells taking a white color (``rgb="255 255 255"``), which overrides the ``col_spec`` for cell 2 and the random color assigned to cell 7. After running OpenMC to obtain PPM files, images should be saved to another format before using them elsewhere. This cuts down the size of the file by orders of magnitude. Most image viewers and editors that can view PPM images can also save to other formats (e.g. `Gimp `_, `IrfanView `_, etc.). However, more likey the user will want to convert to another format on the command line. This is easily accomplished with the ``convert`` command available on most linux distributions as part of the `ImageMagick `_ package. (On Ubuntu: ``sudo apt-get install imagemagick``). Images are then converted like: .. code-block:: sh convert myplot.ppm myplot.png Plotting in 3D -------------- .. image:: ../_images/3dgeomplot.png :height: 200px See below for a simple example of a plots xml file that demonstrates the capabilities of 3D voxel plots. .. code-block:: xml myplot 0 0 0 10 10 10 500 500 500 Voxel plots are built the same way 2D slice plots are, by determining the cell or material id of a particle at the center of each voxel. In this example, the space covered is the cube between the points (-5,-5,-5) and (5,5,5), with voxel centers 10/500 = 0.02 cm apart. The binary VOXEL files that are produced do not specify any color - instead containing only material or cell ids (material id in this example) - and thus the ``background``, ``col_spec``, and ``mask`` elements are not used. If no cell is found at a voxel center, an id of -1 is stored. The binary VOXEL files output by OpenMC can not be viewed directly by any existing viewers. In order to view them, they must be converted into a standard mesh format that can be viewed in ParaView, Visit, etc. This typically will compress the size of the file significantly. The provided utility voxel.py accomplishes this for SILO: .. code-block:: sh /src/utils/voxel.py myplot.voxel -o output.silo and VTK file formats: .. code-block:: sh /src/utils/voxel.py myplot.voxel --vtk -o output.vti To use this utility you need either * `Silomesh `_ or * `VTK `_ with python bindings - On Ubuntu, these are easily obtained with ``sudo apt-get install python-vtk`` Users can process the binary into any other format if desired by following the example of voxel.py. For the binary file structure, see :ref:`devguide_voxel`. Once processed into a standard 3D file format, colors and masks can be defined using the stored id numbers to better explore the geometry. The process for doing this will depend on the 3D viewer, but should be straightforward. .. image:: ../_images/3dba.png :height: 200px .. note:: 3D voxel plotting can be very computer intensive for the viewing program (Visit, Paraview, etc.) if the number of voxels is large (>10 million or so). Thus if you want an accurate picture that renders smoothly, consider using only one voxel in a certain direction. For instance, the 3D pin lattice figure at the beginning of this section was generated with a 500x500x1 voxel mesh, which allows for resolution of the cylinders without wasting too many voxels on the axial dimension. ------------------- Tally Visualization ------------------- Tally results are saved in both a text file (tallies.out) as well as a binary statepoint file. While the tallies.out file may be fine for simple tallies, in many cases the user requires more information about the tally or the run, or has to deal with a large number of result values (e.g. for mesh tallies). In these cases, extracting data from the statepoint file via Python scripting is the preferred method of data analysis and visualization. Data Extraction --------------- A great deal of information is available in statepoint files (See :ref:`devguide_statepoint`), most of which is easily extracted by the provided utility statepoint.py. This utility provides a Python class to load statepoints and extract data - it is used in many of the provided plotting utilities, and can be used in user-created scripts to carry out manipulations of the data. To read tallies using this utility, make sure statepoint.py is in your PYTHONPATH, and then import the class, instantiate it, and call read_results: .. code-block:: python from statepoint import StatePoint sp = StatePoint('statepoint.100.binary') sp.read_results() At this point the user can extract entire scores from tallies into a data dictionary containing numpy arrays: .. code-block:: python tallyid = 1 score = 'flux' data = sp.extract_results(tallyid, score) means = data['means'] print data.keys() The results from this function contain all filter bins (all mesh points, all energy groups, etc.), which can be reshaped with the bin ordering also contained in the output dictionary. This is the best choice of output for easily integrating ranges of data. Alternatively the user can extract specific values for a single score/filter combination: .. code-block:: python tallyid = 1 score = 'flux' filters = [('mesh', (1, 1, 5)), ('energyin', 0)] value, error = sp.get_value(tallyid, filters, score) In the future more documentaion may become available here for statepoint.py and the data extraction functions of StatePoint objects. However, for now it is up to the user to explore the classes in statepoint.py to discover what data is available in StatePoint objects (we highly recommend interactively exploring with `IPython `_). Many exmaples can be found by looking through the other utilies that use statepoint.py, and a few common visualization tasks will be described here in the following sections. Plotting in 2D -------------- .. image:: ../_images/plotmeshtally.png :height: 200px For simple viewing of 2D slices of a mesh plot, the utility plot_mesh_tally.py is provided. This utility provides an interactive GUI to explore and plot mesh tallies for any scores and filter bins. It requires statepoint.py, as well as `PyQt `_. .. image:: ../_images/fluxplot.png :height: 200px Alternatively, the user can write their own Python script to manipulate the data appropriately. Consider a run where the first tally contains a 105x105x20 mesh over a small core, with a flux score and two energyin filter bins. To explicitly extract the data and create a plot with gnuplot, the following script can be used. The script operates in several steps for clarity, and is not necessarily the most efficient way to extract data from large mesh tallies. This creates the two heatmaps in the previous figure. .. code-block:: python #!/usr/bin/env python import os import statepoint # load and parse the statepoint file sp = statepoint.StatePoint('statepoint.300.binary') sp.read_results() tallyid = 0 # This is tally 1 score = 0 # This corresponds to flux (see tally.scores) # get mesh dimensions meshid = sp.tallies[tallyid].filters['mesh'].bins[0] for i,m in enumerate(sp.meshes): if m.id == meshid: mesh = m break nx,ny,nz = mesh.dimension # loop through mesh and extract values to python dictionaries thermal = {} fast = {} for x in range(1,nx+1): for y in range(1,ny+1): for z in range(1,nz+1): val,err = sp.get_value(tallyid, [('mesh',(x,y,z)),('energyin',0)], score) thermal[(x,y,z)] = val val,err = sp.get_value(tallyid, [('mesh',(x,y,z)),('energyin',1)], score) fast[(x,y,z)] = val # sum up the axial values and write datafile for gnuplot with open('meshdata.dat','w') as fh: for x in range(1,nx+1): for y in range(1,ny+1): thermalval = 0. fastval = 0. for z in range(1,nz+1): thermalval += thermal[(x,y,z)] fastval += fast[(x,y,z)] fh.write("{} {} {} {}\n".format(x,y,thermalval,fastval)) # write gnuplot file with open('tmp.gnuplot','w') as fh: fh.write(r"""set terminal png size 1000 400 set output 'fluxplot.png' set nokey set autoscale fix set multiplot layout 1,2 title "Pin Mesh Flux Tally" set title "Thermal" plot 'meshdata.dat' using 1:2:3 with image set title "Fast" plot 'meshdata.dat' using 1:2:4 with image """) # make plot os.system("gnuplot < tmp.gnuplot") Plotting in 3D -------------- .. image:: ../_images/3dcore.png :height: 200px As with 3D plots of the geometry, meshtally data needs to be put into a standard format for viewing. The utility statepoint_3d.py is provided to accomplish this for both VTK and SILO. By default statepoint_3d.py processes a statepoint into a 3D file with all mesh tallies and filter/score combinations, .. code-block:: sh /src/utils/statepoint_3d.py -o output.silo /src/utils/statepoint_3d.py --vtk -o output.vtm but it also provides several command-line options to selectively process only certain data arrays in order to keep file sizes down. .. code-block:: sh /src/utils/statepoint_3d.py --tallies 2,4 --scores 4.1,4.3 -o output.silo /src/utils/statepoint_3d.py --filters 2.energyin.1 --vtk -o output.vtm All available options for specifying a subset of tallies, scores, and filters can be listed with the ``--list`` or ``-l`` command line options. .. note:: Note that while SILO files can contain multiple meshes in one file, VTK needs to use a multi-block dataset, which stores each mesh piece in a different file in a subfolder. All meshes can be loaded at once with the main VTM file, or each VTI file in the subfolder can be loaded individually. Alternatively, the user can write their own Python script to manipulate the data appropriately before insertion into a SILO or VTK file. For instance, if the data has been extracted as was done in the 2D plotting example script above, a SILO file can be created with: .. code-block:: python import silomesh as sm sm.init_silo("fluxtally.silo") sm.init_mesh('tally_mesh', *mesh.dimension, *mesh.lower_left, *mesh.upper_right) sm.init_var('flux_tally_thermal') for x in range(1,nx+1): for y in range(1,ny+1): for z in range(1,nz+1): sm.set_value(float(thermal[(x,y,z)]),x,y,z) sm.finalize_var() sm.init_var('flux_tally_fast') for x in range(1,nx+1): for y in range(1,ny+1): for z in range(1,nz+1): sm.set_value(float(fast[(x,y,z)]),x,y,z) sm.finalize_var() sm.finalize_mesh() sm.finalize_silo() and the equivalent VTK file with: .. code-block:: python import vtk grid = vtk.vtkImageData() grid.SetDimensions(nx+1,ny+1,nz+1) grid.SetOrigin(*mesh.lower_left) grid.SetSpacing(*mesh.width) # vtk cell arrays have x on the inners, so we need to reorder the data idata = {} for x in range(nx): for y in range(ny): for z in range(nz): i = z*nx*ny + y*nx + x idata[i] = (x,y,z) vtkfastdata = vtk.vtkDoubleArray() vtkfastdata.SetName("fast") for i in range(nx*ny*nz): vtkfastdata.InsertNextValue(fast[idata[i]]) vtkthermaldata = vtk.vtkDoubleArray() vtkthermaldata.SetName("thermal") for i in range(nx*ny*nz): vtkthermaldata.InsertNextValue(thermal[idata[i]]) grid.GetCellData().AddArray(vtkfastdata) grid.GetCellData().AddArray(vtkthermaldata) writer = vtk.vtkXMLImageDataWriter() writer.SetInput(grid) writer.SetFileName('tally.vti') writer.Write() Getting Data into MATLAB ------------------------ There is currently no front-end utility to dump tally data to MATLAB files, but the process is straightforward. First extract the data using a custom Python script with statepoint.py, put the data into appropriately-shaped numpy arrays, and then use the `Scipy MATLAB IO routines `_ to save to a MAT file. Note that the data contained in the output from ``StatePoint.extract_result`` is already in a Numpy array that can be reshaped and dumped to MATLAB in one step. ---------------------------- Particle Track Visualization ---------------------------- .. image:: ../_images/Tracks.png :height: 200px OpenMC can dump particle tracks—the position of particles as they are transported through the geometry. There are two ways to make OpenMC output tracks: all particle tracks through a commandline argument or specific particle tracks through settings.xml. Running OpenMC with the argument "-t", "-track", or "--track" will cause a track file to be created for every particle transported in the code. The settings.xml file can dictate that specific particle tracks are output. These particles are specified withen a ''track'' element. The ''track'' element should contain triplets of integers specifying the batch, generation, and particle numbers, respectively. For example, to output the tracks for particles 3 and 4 of batch 1 and generation 2 the settings.xml file should contain: .. code-block:: xml 1 2 3 1 2 4 After running OpenMC, the directory should contain a file of the form "track_(batch #)_(generation #)_(particle #).(binary or h5)" for each particle tracked. These track files can be converted into VTK poly data files with the "track.py" utility. The usage of track.py is of the form "track.py [-o OUT] IN" where OUT is the optional output filename and IN is one or more filenames describing track files. The default output name is "track.pvtp". A common usage of track.py is "track.py track*.binary" which will use the data from all binary track files in the directory to write a "track.pvtp" VTK output file. The .pvtp file can then be read and plotted by 3d visualization programs such as Paraview. ---------------------- Source Site Processing ---------------------- For eigenvalue problems, OpenMC will store information on the fission source sites in the statepoint file by default. For each source site, the weight, position, sampled direction, and sampled energy are stored. To extract this data from a statepoint file, the statepoint.py Python module can be used. Below is an example of an interactive ipython session using the statepoint.py Python module: .. code-block:: python In [1]: import statepoint In [2]: sp = statepoint.StatePoint('statepoint.100.h5') In [3]: sp.read_source() In [4]: len(sp.source) Out[4]: 1000 In [5]: sp.source[0:10] Out[5]: [, , , , , , , , , ] In [6]: site = sp.source[0] In [7]: site.weight Out[7]: 1.0 In [8]: site.xyz Out[8]: array([ 2.21980946, -8.92686048, 87.93720485]) In [9]: site.uvw Out[9]: array([ 0.06740523, 0.50612814, 0.85982024]) In [10]: site.E Out[10]: 0.93292326356564159