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Started intro in theory/methods documentation.
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Introduction
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============
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The physical process by which a population of particles evolves over time is
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governed by a number of `probability distributions`_. For instance, given a
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particle traveling through some material, there is a probability distribution
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for the distance it will travel until its next collision (an exponential
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distribution). Then, when it collides with a nucleus, there is associated
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probability of undergoing each possible reaction with that nucleus. While the
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behavior of any single particle is unpredictable, the average behavior of a
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large population of particles originating from the same source is well defined.
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If the probability distributions that govern the transport of a particle are
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known, the process of single particles randomly streaming and colliding with
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nuclei can be simulated directly with computers using a technique known as
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`Monte Carlo`_ simulation. If enough particles are simulated this way, the
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average behavior can be determined to within arbitrarily small statistical
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error, a fact guaranteed by the `central limit theorem`_. To be more precise,
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the central limit theorem tells us that the variance of the sample mean of some
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physical parameter being estimated with Monte Carlo will be inversely
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proportional to the number of realizations, i.e. the number of particles we
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simulate:
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.. math::
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\sigma^2 \propto \frac{1}{N}.
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where :math:`\sigma^2` is the variance of the sample mean and :math:`N` is the
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number of realizations.
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---------------------
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Criticality Algorithm
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---------------------
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.. _probability distributions: http://en.wikipedia.org/wiki/Probability_distribution
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.. _Monte Carlo: http://en.wikipedia.org/wiki/Monte_Carlo_method
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.. _central limit theorem: http://en.wikipedia.org/wiki/Central_limit_theorem
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@ -4,7 +4,11 @@
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Publications
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============
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- Paul K. Romano and Beonit Forget, "The OpenMC Monte Carlo Particle Transport
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- Paul K. Romano and Benoit Forget, "Reducing Parallel Communication in Monte
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Carlo Simulations via Batch Statistics," *Trans. Am. Nucl. Soc.*, Submitted
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(2012).
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- Paul K. Romano and Benoit Forget, "The OpenMC Monte Carlo Particle Transport
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Code," *Annals of Nuclear Energy*, Submitted (2012).
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- Andrew R. Siegel, Kord Smith, Paul K. Romano, Benoit Forget, and Kyle Felker,
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@ -22,7 +22,7 @@ quantity one is interested in) very accurately.
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Using Monte Carlo methods to determine the average behavior of various physical
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quantities in a nuclear reactor is quite different from other means of solving
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the same problem. The other class of methods for determining the behavior of
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neutrons and reactions rates in a reactor is so-called `determinstic`_
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neutrons and reactions rates in a reactor is so-called `deterministic`_
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methods. In these methods, the starting point is not randomly simulating
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particles but rather writing an equation that describes the average behavior of
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the particles. The equation that describes the average behavior of neutrons is
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@ -138,7 +138,7 @@ and `Volume II`_. You may also find it helpful to review the following terms:
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.. _nuclear reactor: http://en.wikipedia.org/wiki/Nuclear_reactor
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.. _Monte Carlo: http://en.wikipedia.org/wiki/Monte_Carlo_method
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.. _fission: http://en.wikipedia.org/wiki/Nuclear_fission
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.. _determinstic: http://en.wikipedia.org/wiki/Deterministic_algorithm
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.. _deterministic: http://en.wikipedia.org/wiki/Deterministic_algorithm
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.. _neutron transport: http://en.wikipedia.org/wiki/Neutron_transport
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.. _discretization: http://en.wikipedia.org/wiki/Discretization
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.. _constructive solid geometry: http://en.wikipedia.org/wiki/Constructive_solid_geometry
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