From 413a58a363ee8fbedeffa652f068f647f0fcb0dc Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 1 Aug 2016 11:15:48 -0500 Subject: [PATCH] Change a few mentions of ACE format cross sections and update manpage --- man/man1/openmc.1 | 16 +++++++++++++--- readme.rst | 2 +- 2 files changed, 14 insertions(+), 4 deletions(-) diff --git a/man/man1/openmc.1 b/man/man1/openmc.1 index e69360a7c..7f18ab28a 100644 --- a/man/man1/openmc.1 +++ b/man/man1/openmc.1 @@ -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 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 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 tag in +.I settings.xml\fP. .SH LICENSE Copyright \(co 2011-2016 Massachusetts Institute of Technology. .PP diff --git a/readme.rst b/readme.rst index 03964d943..90484ad49 100644 --- a/readme.rst +++ b/readme.rst @@ -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