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Change a few mentions of ACE format cross sections and update manpage

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Paul Romano 2016-08-01 11:15:48 -05:00
parent aaefad9e2e
commit 413a58a363
2 changed files with 14 additions and 4 deletions
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16
man/man1/openmc.1
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@ -3,7 +3,7 @@
openmc \- Executes the OpenMC Monte Carlo code
.SH DESCRIPTION
This command is used to execute the OpenMC Monte Carlo code. It is assumed that
a set of XML input files has already been created and that ACE format cross
a set of XML input files has already been created and that HDF5 format cross
sections are available.
.SH SYNOPSIS
\fBopenmc\fR [\fIoptions\fR] [\fIpath\fR]
@ -40,11 +40,21 @@ The behavior of
.B openmc
is affected by the following environment variables.
.TP
.B CROSS_SECTIONS
.B OPENMC_CROSS_SECTIONS
Indicates the default path to the cross_sections.xml summary file that is used
to locate ACE format cross section libraries if the user has not specified the
to locate HDF5 format cross section libraries if the user has not specified the
<cross_sections> tag in
.I settings.xml\fP.
.TP
.B OPENMC_MG_CROSS_SECTIONS
Indicates the default path to the mgxs.xml file that contains multi-group cross
section libraries if the user has not specified the <cross_sections> tag in
.I settings.xml\fP.
.TP
.B OPENMC_MULTIPOLE_LIBRARY
Indicates the default path to a directory containing windowed multipole data if
the user has not specified the <multipole_library> tag in
.I settings.xml\fP.
.SH LICENSE
Copyright \(co 2011-2016 Massachusetts Institute of Technology.
.PP

2
readme.rst
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@ -7,7 +7,7 @@ OpenMC Monte Carlo Particle Transport Code
The OpenMC project aims to provide a fully-featured Monte Carlo particle
transport code based on modern methods. It is a constructive solid geometry,
continuous-energy transport code that uses ACE format cross sections. The
continuous-energy transport code that uses HDF5 format cross sections. The
project started under the Computational Reactor Physics Group at MIT.
Complete documentation on the usage of OpenMC is hosted on Read the Docs at