crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 22:26:08 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Merge pull request #946 from paulromano/eq-hash

Browse source 
Ensure mutable objects are not hashable
This commit is contained in:
Sterling Harper 2017-12-20 01:51:12 -05:00 • committed by GitHub
commit a149ef42a0
No known key found for this signature in database
GPG key ID: 4AEE18F83AFDEB23
36 changed files with 1961 additions and 2835 deletions
Download patch file Download diff file Expand all files Collapse all files

4
docs/source/conf.py
View file

@ -27,8 +27,8 @@ except ImportError:
MOCK_MODULES = ['numpy', 'numpy.polynomial', 'numpy.polynomial.polynomial',
'numpy.ctypeslib', 'scipy', 'scipy.sparse', 'scipy.interpolate',
'scipy.integrate', 'scipy.optimize', 'scipy.special',
'scipy.stats','h5py', 'pandas', 'uncertainties', 'openmoc',
'openmc.data.reconstruct']
'scipy.stats', 'h5py', 'pandas', 'uncertainties',
'matplotlib.pyplot','openmoc', 'openmc.data.reconstruct']
sys.modules.update((mod_name, MagicMock()) for mod_name in MOCK_MODULES)
import numpy as np

23
docs/source/io_formats/materials.rst
View file

@ -92,20 +92,8 @@ Each ``material`` element can have the following attributes or sub-elements:
.. note:: If one nuclide is specified in atom percent, all others must also
be given in atom percent. The same applies for weight percentages.
An optional attribute/sub-element for each nuclide is ``scattering``. This
attribute may be set to "data" to use the scattering laws specified by the
cross section library (default). Alternatively, when set to "iso-in-lab",
the scattering laws are used to sample the outgoing energy but an
isotropic-in-lab distribution is used to sample the outgoing angle at each
scattering interaction. The ``scattering`` attribute may be most useful
when using OpenMC to compute multi-group cross-sections for deterministic
transport codes and to quantify the effects of anisotropic scattering.
*Default*: None
.. note:: The ``scattering`` attribute/sub-element is not used in the
multi-group :ref:`energy_mode`.
:sab:
Associates an S(a,b) table with the material. This element has an
attribute/sub-element called ``name``. The ``name`` attribute
@ -119,6 +107,17 @@ Each ``material`` element can have the following attributes or sub-elements:
.. note:: This element is not used in the multi-group :ref:`energy_mode`.
:isotropic:
The ``isotropic`` element indicates a list of nuclides for which elastic
scattering should be treated as though it were isotropic in the laboratory
system. This element may be most useful when using OpenMC to compute
multi-group cross-sections for deterministic transport codes and to quantify
the effects of anisotropic scattering.
*Default*: No nuclides are treated as have isotropic elastic scattering.
.. note:: This element is not used in the multi-group :ref:`energy_mode`.
:macroscopic:
The ``macroscopic`` element is similar to the ``nuclide`` element, but,
recognizes that some multi-group libraries may be providing material