Fixes to documentation

docs/source/methods/cmfd.rst

@@ -28,7 +28,7 @@ directions. An example of this is shown in the following expression:
     :label: not1
 
     \sum\limits_{u\in(x,y,z)}\left\langle\overline{J}^{u,g}_{l+1/2,m,n}
-    \Delta_m^v\Delta_n^w\right\rangle 
+    \Delta_m^v\Delta_n^w\right\rangle
 
 Here, :math:`u` takes on each direction one at a time. The parameter :math:`J`
 is surface area-averaged over the transverse indices :math:`m` and :math:`n`
@@ -142,7 +142,7 @@ defined from MC tallies as follows:
    {\left\langle\overline{\overline\phi}_{l,m,n}^h
    \Delta_l^u\Delta_m^v\Delta_n^w\right\rangle}
 
-and 
+and
 
 .. math::
    :label: xs3
@@ -306,7 +306,7 @@ interior cell,
    + \left(\tilde{D}_{l-1/2,m,n}^{u,g} +
    \tilde{D}_{l+1/2,m,n}^{u,g} - \hat{D}_{l-1/2,m,n}^{u,g} +
    \hat{D}_{l+1/2,m,n}^{u,g}\right)\overline{\overline{\phi}}_{l,m,n}^g
-   \\ + 
+   \\ +
    \left. \left(-\tilde{D}_{l+1/2,m,n}^{u,g} +
    \hat{D}_{l+1/2,m,n}^{u,g}\right)\overline{\overline{\phi}}_{l+1,m,n}^g
    \right] +
@@ -318,7 +318,7 @@ interior cell,
 
 It should be noted that before substitution, eq. :eq:`eq_neut_bal` was divided
 by the volume of the cell, :math:`\Delta_l^u\Delta_m^v\Delta_n^w`. Equation
-:eq:`eq_cmfd_sys` can be represented in operator form as 
+:eq:`eq_cmfd_sys` can be represented in operator form as
 
 .. math::
    :label: eq_CMFDopers
@@ -349,7 +349,7 @@ and energy group. This is represented as
    p_{l,m,n}^g =
    \frac{\sum_{h=1}^{G}\overline{\overline{\nu_f\Sigma}}^{h\rightarrow
    g}_{f_{l,m,n}}\overline{\overline{\phi}}_{l,m,n}^h\Delta_l^u\Delta_m^v
-   \Delta_n^w}{\sum_n\sum_m\sum_l\sum_{h=1}^{G}\overline{ 
+   \Delta_n^w}{\sum_n\sum_m\sum_l\sum_{h=1}^{G}\overline{
    \overline{\nu_f\Sigma}}^{h\rightarrow
    g}_{f_{l,m,n}}\overline{\overline{\phi}}_{l,m,n}^h\Delta_l^u\Delta_m^v
    \Delta_n^w}.
@@ -478,14 +478,14 @@ no fission neutrons appear with energies in the thermal group.
 .. figure:: ../_images/loss.png
    :scale: 50
 
-   Sparsity of Neutron Loss Operator 
+   Sparsity of Neutron Loss Operator
 
 .. _fig_prod:
 
 .. figure:: ../_images/prod.png
    :scale: 50
 
-   Sparsity of Neutron Production Operator 
+   Sparsity of Neutron Production Operator
 
 To solve the eigenvalue problem with these matrices, different source iteration
 and linear solvers can be used. The most common source iteration solver used is
@@ -511,7 +511,7 @@ implemented to obtain eigenvalue and multigroup fluxes as described in [Gill]_
 and [Knoll]_. This method is not the primary one used, but has gotten recent
 attention due to its coupling advantages to other physics such as thermal
 hydraulics. Once multigroup fluxes are obtained, a normalized fission source is
-calculated in the code using eq. :eq:`eq_cmfd_psrc` directly. 
+calculated in the code using eq. :eq:`eq_cmfd_psrc` directly.
 
 The next step in the process is to compute weight adjustment factors. These are
 calculated by taking the ratio of the expected number of neutrons from the CMFD
@@ -523,7 +523,7 @@ the current MC source, OpenMC sums the statistical
 weights of neutrons from the source bank on a given spatial and energy mesh.
 Once weight adjustment factors were calculated, each neutron's statistical
 weight in the source bank was modified according to its location and energy.
-Examples of CMFD simulations using OpenMC can be found in [Herman_Thesis]_.
+Examples of CMFD simulations using OpenMC can be found in [HermanThesis]_.
 
 ----------
 References
@@ -536,23 +536,23 @@ References
 .. [Gill] Daniel F. Gill. *Newton-Krylov methods for the solution of the k-eigenvalue problem in
           multigroup neutronics calculations*. Ph.D. thesis, Pennsylvania State University, 2010.
 
-.. [Hebert] Alain Hebert. *Applied reactor physics*. Presses Internationales Polytechnique, 
+.. [Hebert] Alain Hebert. *Applied reactor physics*. Presses Internationales Polytechnique,
             Montreal, 2009.
 
 .. [Herman] Bryan R. Herman, Benoit Forget, Kord Smith, and Brian N. Aviles. Improved
             diffusion coefficients generated from Monte Carlo codes. In *Proceedings of M&C
             2013*, Sun Valley, ID, USA, May 5 - 9, 2013.
 
-.. [Herman_Thesis] Bryan R. Herman. *Monte Carlo and Thermal Hydraulic Coupling using
-                   Low-Order Nonlinear Diffusion Acceleration*. Sc.D. thesis,
-                   Massachusetts Institute of Technology, 2014.
+.. [HermanThesis] Bryan R. Herman. *Monte Carlo and Thermal Hydraulic Coupling using
+                  Low-Order Nonlinear Diffusion Acceleration*. Sc.D. thesis,
+                  Massachusetts Institute of Technology, 2014.
 
 .. [Knoll] D.A. Knoll, H. Park, and C. Newman. *Acceleration of k-eigenvalue/criticality
            calculations using the Jacobian-free Newton-Krylov method*. Nuclear Science and
            Engineering, 167:133–140, 2011.
 
 .. [Park] H. Park, D.A. Knoll, and C.K. Newman. *Nonlinear acceleration of transport
-          criticality problems*. Nuclear Science and Engineering, 172:52–65, 2012. 
+          criticality problems*. Nuclear Science and Engineering, 172:52–65, 2012.
 
 .. [Rhodes] Joel Rhodes and Malte Edenius. *CASMO-4 --- A Fuel Assembly Burnup Program.
             User’s Manual*. Studsvik of America, ssp-09/443-u rev 0, proprietary edition, 2001.