From 8f20c20af045267ee6729eeedd0b3c75243472f4 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 6 Sep 2022 16:01:46 -0500 Subject: [PATCH] Move cross_sections.rst to data.rst and rename section header --- docs/source/usersguide/{cross_sections.rst => data.rst} | 8 ++++---- docs/source/usersguide/index.rst | 2 +- 2 files changed, 5 insertions(+), 5 deletions(-) rename docs/source/usersguide/{cross_sections.rst => data.rst} (99%) diff --git a/docs/source/usersguide/cross_sections.rst b/docs/source/usersguide/data.rst similarity index 99% rename from docs/source/usersguide/cross_sections.rst rename to docs/source/usersguide/data.rst index 0cbb581bd4..6a135df76a 100644 --- a/docs/source/usersguide/cross_sections.rst +++ b/docs/source/usersguide/data.rst @@ -1,8 +1,8 @@ -.. _usersguide_cross_sections: +.. _usersguide_data: -=========================== -Cross Section Configuration -=========================== +================== +Data Configuration +================== In order to run a simulation with OpenMC, you will need cross section data for each nuclide or material in your problem. OpenMC can be run in continuous-energy diff --git a/docs/source/usersguide/index.rst b/docs/source/usersguide/index.rst index fab353c773..511bdc6cef 100644 --- a/docs/source/usersguide/index.rst +++ b/docs/source/usersguide/index.rst @@ -13,7 +13,7 @@ essential aspects of using OpenMC to perform simulations. beginners install - cross_sections + data basics materials geometry