CAD-to-OpenMC 0.2.2

Package to automagically convert step-gometries to h5m descriptions for neutronics by OpenMC

CAD_to_OpenMC

This is intended to be a python package heavily inspired by Paramak, and borrows a lot from step_to_h5m. It's "raison d'etre" is to establish an open source-based link between CAD tools in general and the neutron transport code OpenMC.

Although most CAD-tools use some other internal and/or native representation for geometry, most, if not all, will be able to export to the STEP-file format. Therefore this is the format we use

CAD_to_OpenMC uses cadQuery and its links to OCCT to enable import and imprinting/merging algorithms. This is a way of solving the problem with touching surfaces.

The code structure relies on a main class Assembly, which maintains the geometry in terms of a list of instances of the subclass Entity. A geometry is imported from a (set of) .step files into the entity-list. This list is passed on to a mesher-class which generates a meshed geometry.

To install/set up in a virtual python environment

replace <name> with an arbitrary name for your virtual environment

1. In the directory where you want your environment to reside do: python -m venv <name>
2. Activate the environment: source <name>/bin/activate
3. Build and install moab (if not already installed). The moab team relies on conda for standard installation but are working on a pip-based solution. Once that is done moab would simply be added to the requirements-file instead.
   1. Clone the moab code-repository: e.g. git clone [e-mail]:fathomteam/moab.git
   2. Configure and build the code:

     mkdir build;
     cd build; cmake .. -DENABLE_PYMOAB=1 -DCMAKE_INSTALL_PREFIX=<name>;
     make;
     make install;
   

   3. Additionally you will need to build the python interface layer.

     cd pymoab
     sudo python setup.py install
   

4. Install the main package: pip install CAD_to_OpenMC. This will pip-install all the required python packages in the virtual environment. This ensures that no additional conflicts are introduced with the system python.

Should you wish to install the development version of this package you may do so by cloning this repository and replace the last command by: pip install <path/to/repo>. This procedure will build and install the python package locally directly from source.

5. Optionally install the msh refinement tool mmg (https://www.mmgtools.org), which may be run in conjunction with the cq/stl-mesher backend to avoid the high aspect ratio triangles that this backend tends to produce. Arch-linux users may install this from the AUR, otherwise get the source (and build from that) or binary builds from the mmg-site.

Run a test case:

The follwing code-snippet can now be run to explore the capabilities of Assembly/step_to_h5m. We supply a couple of example .step-files in the examples directory. In this example we'll be using a geometry with a set of 7 pin-cells.

  import CAD_to_OpenMC.assembly as ab
  a=ab.Assembly()
  a.stp_files=["examples/7pin.step"]
  a.import_stp_files()
  a.solids_to_h5m()

Unless anything else is specified this procedure simply uses the default CAD_to_OpenMC parameters to create meshes using the default choice of meshing backend - namely gmsh. E.g. for the "gmsh"-backend this means sampling curves 20 times, a minimum mesh-element size of 0.1, and a maximum mesh element size of 10. This procedure will in turn call OCP and gmsh to produce a mesh with merged surfaces in the output file "dagmc.h5m"

The other available meshing backend is the stl-export from CadQuery (accessible by setting backend='stl') which uses the parameters tolerance and angular_tolerance to set meshing quality.

Parameters are changed by means of altering entries in the mesher_config-dictionary defined in the assembly module root namespace. Like:

 ab.mesher_config['min_mesh_size']=0.2

Below is a list of the available parameters and their meanings:

min_mesh_size

Minimum mesh element size (gmsh backend)

max_mesh_size

Maximum mesh element size (gmsh backend)

curve_samples

The number of point samples used to approximate a curve, 1D-mesh. (gmsh backend)

mesh_algorithm

Integer specifying which meshing algorithm to use (gmsh backend) 1: Adaptive algorithm - most often the most robust choice.

vetoed

A list of surfaces that should be excluded from meshing. Useful when some surface fails for whatever reason. Be aware that this may make your geometry non-watertight.

threads

The number of threads to be used to speed up the meshing algorithms. Useful for multicore-computers.

tolerance

angular_tolerance

Relative angular mesh tolerance (stl backend) Lower this to get a better angular resolution.

refine

After the initial meshing step is done, should the mesh be refined. This option has more than one meaning. If the cq/stl-backend is active and refinement is non-zero or true, the mesh-refinment tool (mmg)[https://www.mmgtools.org] is called in sequence on each surface. If the gmsh-backend is active and refine is non-zero the gmsh-refinement tool is called on the full geometry the given number of times. A value of true simply does refinement once.

Advanced example

For a more advanced example of the use of CAD_to_OpenMC and OpenMC we may turn to the Zero Power Reactor Experiment. This was a full-scale reactor experiment that was carried out at Oak Rodge TN in the 1960's. Copenhagen Atomics provides a CAD-drawn model of this experiment, extracted from the original reports and drawings from the original experiment, in the form of a step-file. To get access simply clone the zpre github repository and run the scripts:

git clone https://www.github.com/openmsr/zpre
cd zpre
bash run.sh

The run.sh-script will the ask you what kind of calculation you'd like to perform. As a first run you might choose to ask OpenMC to simply plot the geometry of the reactor (option 2). If this is the first time you run the script, this triggers a surface-meshing operation to be performed (Be aware that by default this creates a large amount of console output - this is to be expected). Dring the surface meshing operation (by default) a .vtk-file is created in addition to the .h5m-file that OpenMC (and DAGMC) needs. This is for convenience so you may inspect the created mesh using e.g. paraview, if you have access to that. If you have paraview installed the call paraview h5m_files/zpre.vtk should yield a geometry like this .

Once this process has finished, there should now be a file zpre.h5m inside the h5m_files directory, and a set of plot_[123].png files. which correspond to XY,XZ, and YZ-slices through the center of the reactor. If all goes well these should look something like this:

XY	XZ	XZ

The colors are chosen arbitrarily amd automatically by the OpenMC-plotting routine, which is why the same geomtrical entity gets a different color in the slices.