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Fixed typos after building and looking at html

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Adam Nelson 2016-06-15 19:36:39 -04:00
parent 6d59516355
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2 changed files with 15 additions and 14 deletions
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15
docs/source/methods/cross_sections.rst
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@ -75,7 +75,7 @@ are represented using a multi-group library format specific to the OpenMC code.
The format is described in the :ref:`mgxs_lib_spec`.
The data itself can be prepared via traditional paths or directly from a
continuous-energy OpenMC calculation by use of the Python API as is shown in the
Python API :ref:`_notebook_mgxs_part_iv` example notebook. This multi-group
:ref:`notebook_mgxs_part_iv` example notebook. This multi-group
library consists of meta-data (such as the energy group structure) and multiple
`xsdata` objects which contains the required microscopic or macroscopic
multi-group data.
@ -83,9 +83,10 @@ multi-group data.
At a minimum, the library must contain the absorption cross section
(:math:`\sigma_{a,g}`) and a scattering matrix. If the problem is an eigenvalue
problem then all fissionable materials must also contain either
a fission production matrix cross section (:math:`\nu\sigma_{f,g\arrow\g'}`), or
both the fission spectrum data (:math:`\chi{g'}`) and a fission production cross
section (:math:`\nu\sigma_{f,g}`), or, . The library must also contain
a fission production matrix cross section
(:math:`\nu\sigma_{f,g\rightarrow g'}`), or
both the fission spectrum data (:math:`\chi_{g'}`) and a fission production
cross section (:math:`\nu\sigma_{f,g}`), or, . The library must also contain
the fission cross section (:math:`\sigma_{f,g}`) or the fission energy release
cross section (:math:`\kappa\sigma_{f,g}`) if the associated tallies are
required by the model using the library.
@ -113,8 +114,8 @@ reaction has occurred:
.. math::
multiplicity_{g \arrow g'} = \frac{\nu_{scatter}\sigma_{s,g \arrow g'}}{
\sigma_{s,g \arrow g'}}
multiplicity_{g \rightarrow g'} = \frac{\nu_{scatter}\sigma_{s,g \rightarrow g'}}{
\sigma_{s,g \rightarrow g'}}
If this scattering multiplication information is not provided in the library
then no weight adjustment will be performed. This is equivalent to neglecting
@ -130,7 +131,7 @@ follows:
.. math::
\sigma_{a,g} = \sigma_{t,g} - \sum_{g'}{\nu_{scatter}\sigma_{s,g \arrow g'}}
\sigma_{a,g} = \sigma_{t,g} - \sum_{g'}\nu_{scatter}\sigma_{s,g \rightarrow g'}
The above method is the same as is usually done with most deterministic solvers.
Note that this method is less accurate than using the scattering multiplication

14
docs/source/methods/physics.rst
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@ -87,7 +87,7 @@ Elastic Scattering
Note that the multi-group mode makes no distinction between elastic or
inelastic scattering reactions. The spceific multi-group scattering
implementation is discussed in the multi-group-scatter_ section.
implementation is discussed in the :ref:`multi-group-scatter` section.
Elastic scattering refers to the process by which a neutron scatters off a
nucleus and does not leave it in an excited. It is referred to as "elastic"
@ -182,7 +182,7 @@ Inelastic Scattering
Note that the multi-group mode makes no distinction between elastic or
inelastic scattering reactions. The spceific multi-group scattering
implementation is discussed in the multi-group-scatter_ section.
implementation is discussed in the :ref:`multi-group-scatter` section.
The major algorithms for inelastic scattering were described in previous
sections. First, a scattering cosine is sampled using the algorithms in
@ -202,7 +202,7 @@ secondary photons from nuclear de-excitation are tracked in OpenMC.
Note that the multi-group mode makes no distinction between elastic or
inelastic scattering reactions. The specific multi-group scattering
implementation is discussed in the multi-group-scatter_ section.
implementation is discussed in the :ref:`multi-group-scatter` section.
These types of reactions are just treated as inelastic scattering and as such
are subject to the same procedure as described in :ref:`inelastic-scatter`. For
@ -229,13 +229,13 @@ incoming energy group is to select a random number (:math:`\xi`) between 0 and
produced from the outgoing group (`g'`) data for the given incoming group (`g`):
.. math::
CDF = \sum_{g'=0}^{h}\Sigma_{s,g \arrow g'}
CDF = \sum_{g'=0}^{h}\Sigma_{s,g \rightarrow g'}
If the scattering data is represented as a Legendre expansion, then the
value of :math:`\Sigma_{s,g \arrow g'}` above is simply the 0th order for the
value of :math:`\Sigma_{s,g \rightarrow g'}` above is the 0th order forthe
given group transfer. If the data is provided as tabular or histogram data, then
the value of :math:`\Sigma_{s,g \arrow g'}` is the sum of all bins of data for a
given `g` and `g'` pair.
:math:`\Sigma_{s,g \rightarrow g'}` is the sum of all bins of data for a given
`g` and `g'` pair.
Now that the outgoing energy is known the change-in-angle, :math:`\mu` can be
determined. If the data is provided as a Legendre expansion, this is done by