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26
docs/source/usersguide/beginners.rst
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@ -8,19 +8,19 @@ A Beginner's Guide to OpenMC
What does OpenMC do?
--------------------
In a nutshell, OpenMC simulates neutral particles (presently only neutrons)
moving stochastically through an arbitrarily defined model that represents an
real-world experimental setup. The experiment could be as simple as a sphere of
metal or as complicated as a full-scale `nuclear reactor`_. This is what's known
as `Monte Carlo`_ simulation. In the case of a nuclear reactor model, neutrons
are especially important because they are the particles that induce `fission`_
in isotopes of uranium and other elements. Knowing the behavior of neutrons
allows one to determine how often and where fission occurs. The amount of energy
released is then directly proportional to the fission reaction rate since most
heat is produced by fission. By simulating many neutrons (millions or billions),
it is possible to determine the average behavior of these neutrons (or the
behavior of the energy produced, or any other quantity one is interested in)
very accurately.
In a nutshell, OpenMC simulates neutral particles (presently neutrons and
photons) moving stochastically through an arbitrarily defined model that
represents an real-world experimental setup. The experiment could be as simple
as a sphere of metal or as complicated as a full-scale `nuclear reactor`_. This
is what's known as `Monte Carlo`_ simulation. In the case of a nuclear reactor
model, neutrons are especially important because they are the particles that
induce `fission`_ in isotopes of uranium and other elements. Knowing the
behavior of neutrons allows one to determine how often and where fission
occurs. The amount of energy released is then directly proportional to the
fission reaction rate since most heat is produced by fission. By simulating
many neutrons (millions or billions), it is possible to determine the average
behavior of these neutrons (or the behavior of the energy produced, or any
other quantity one is interested in) very accurately.
Using Monte Carlo methods to determine the average behavior of various physical
quantities in a system is quite different from other means of solving the same

8
docs/source/usersguide/scripts.rst
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@ -181,10 +181,10 @@ use with OpenMC. This script has the following optional arguments:
``openmc-get-photon-data``
--------------------------
This script downloads `ENDF/B-VII.1 <http://www.nndc.bnl.gov/endf/b7.1/zips/>`_
ENDF data from NNDC for photo-atomic and atomic relaxation sublibraries and
converts it to an HDF5 library for use with photon transport in OpenMC. This
script has the following optional arguments:
This script downloads `ENDF data <http://www.nndc.bnl.gov/endf/b7.1/zips/>`_
from NNDC for photo-atomic and atomic relaxation sublibraries and converts it
to an HDF5 library for use with photon transport in OpenMC. This script has the
following optional arguments:
-b, --batch
Suppress standard in