crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 06:05:58 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Cleaned up automatic binning code for mu filters and updated documentation/rng files

Browse source
This commit is contained in:
Adam Nelson 2015-08-25 20:03:19 -04:00
parent ec788085b3
commit a64255bdc8
5 changed files with 26 additions and 7 deletions
Download patch file Download diff file Expand all files Collapse all files

15
docs/source/usersguide/input.rst
View file

@ -1251,6 +1251,21 @@ The ``<tally>`` element accepts the following sub-elements:
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.
:mu:
A monotonically increasing list of bounding **post-collision**
cosines of the change in a particle's angle (i.e., :math:`\mu`),
which represents a portion of the possible values of :math:'\[-1,1\]'.
For example, spanning all of :math:'\[-1,1\]' with five equi-width
bins can be specified as:
``<filter type="mu" bins="-1.0 -0.6 -0.2 0.2 0.6 1.0" />``
Alternatively, if only one value is provided as a bin, OpenMC will
interpret this to mean the complete range of :math:'\[-1,1\]' should
be automatically subdivided in to the provided value for the bin.
That is, the above example of five equi-width bins spanning
:math:'\[-1,1\]' can be instead written as:
``<filter type="mu" bins="5" />``.
:mesh:
The ``id`` of a structured mesh to be tallied over.