mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 14:15:42 -04:00
Move cross_sections.rst to data.rst and rename section header
This commit is contained in:
parent
c5012996df
commit
8f20c20af0
2 changed files with 5 additions and 5 deletions
|
|
@ -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
|
||||
|
|
@ -13,7 +13,7 @@ essential aspects of using OpenMC to perform simulations.
|
|||
|
||||
beginners
|
||||
install
|
||||
cross_sections
|
||||
data
|
||||
basics
|
||||
materials
|
||||
geometry
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue