use the only directive instead of tags for removing Contents from latex doc

docs/Makefile

@@ -106,14 +106,14 @@ epub:
 	@echo "Build finished. The epub file is in $(BUILDDIR)/epub."
 
 latex: images
-	$(SPHINXBUILD) -t latex -b latex $(ALLSPHINXOPTS) $(BUILDDIR)/latex
+	$(SPHINXBUILD) -b latex $(ALLSPHINXOPTS) $(BUILDDIR)/latex
 	@echo
 	@echo "Build finished; the LaTeX files are in $(BUILDDIR)/latex."
 	@echo "Run \`make' in that directory to run these through (pdf)latex" \
 	      "(use \`make latexpdf' here to do that automatically)."
 
 latexpdf: images
-	$(SPHINXBUILD) -t latex -b latex $(ALLSPHINXOPTS) $(BUILDDIR)/latex
+	$(SPHINXBUILD) -b latex $(ALLSPHINXOPTS) $(BUILDDIR)/latex
 	@echo "Running LaTeX files through pdflatex..."
 	make -C $(BUILDDIR)/latex all-pdf
 	@echo "pdflatex finished; the PDF files are in $(BUILDDIR)/latex."

docs/source/conf.py

@@ -35,12 +35,7 @@ source_suffix = '.rst'
 #source_encoding = 'utf-8'
 
 # The master toctree document.
-if tags.has('latex'):
-    master_doc = 'index_tex'
-    exclude_patterns = ['index.rst']
-else:
-    master_doc = 'index'
-    exclude_patterns = ['index_tex.rst']
+master_doc = 'index'
 
 # General information about the project.
 project = u'OpenMC'
@@ -189,7 +184,7 @@ htmlhelp_basename = 'openmcdoc'
 # Grouping the document tree into LaTeX files. List of tuples
 # (source start file, target name, title, author, documentclass [howto/manual]).
 latex_documents = [
-  ('index_tex', 'openmc.tex', u'OpenMC Documentation',
+  ('index', 'openmc.tex', u'OpenMC Documentation',
    u'Massachusetts Institute of Technology', 'manual'),
 ]
 

docs/source/index.rst

@@ -18,9 +18,11 @@ free to send a message to the User's Group `mailing list`_.
 .. _Massachusetts Institute of Technology: http://web.mit.edu
 .. _mailing list: https://groups.google.com/forum/?fromgroups=#!forum/openmc-users
 
---------
-Contents
---------
+.. only:: html
+
+    --------
+    Contents
+    --------
 
 .. toctree::
     :maxdepth: 1

docs/source/index_tex.rst

@@ -1,31 +0,0 @@
-===========================
-The OpenMC Monte Carlo Code
-===========================
-
-OpenMC is a Monte Carlo particle transport simulation code focused on neutron
-criticality calculations. It is capable of simulating 3D models based on
-constructive solid geometry with second-order surfaces. The particle interaction
-data is based on ACE format cross sections, also used in the MCNP and Serpent
-Monte Carlo codes.
-
-OpenMC was originally developed by members of the `Computational Reactor Physics
-Group`_ at the `Massachusetts Institute of Technology`_ starting
-in 2011. Various universities, laboratories, and other organizations now
-contribute to the development of OpenMC. For more information on OpenMC, feel
-free to send a message to the User's Group `mailing list`_.
-
-.. _Computational Reactor Physics Group: http://crpg.mit.edu
-.. _Massachusetts Institute of Technology: http://web.mit.edu
-.. _mailing list: https://groups.google.com/forum/?fromgroups=#!forum/openmc-users
-
-.. toctree::
-    :maxdepth: 1
-
-    quickinstall
-    releasenotes/index
-    methods/index
-    usersguide/index
-    devguide/index
-    publications
-    license
-    developers