Added description of ACE Law 1 in documentation.

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Paul Romano 2012-07-25 15:53:23 -04:00
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@ -220,7 +220,55 @@ for the data.
ACE Law 1 - Tabular Equiprobable Energy Bins
++++++++++++++++++++++++++++++++++++++++++++
In the tabular equiprobable bin representation, an array of equiprobably
outgoing energy bins is given for a number of incident energies. While the
representation itself is simple, the complexity lies in how one interpolates
between incident as well as outgoing energies on such a table. If one does
simple interpolation between tables for neighboring incident energies, it is
possible for the resulting energies to violate laws governing the kinematics,
i.e. the outgoing energy may be outside the range of available energy in the
reaction.
To avoid this situation, the accepted practice is to use a process known as
scaled interpolation [Doyas]_. First, we find the tabulated incident energies
which bound the actual incoming energy of the particle, i.e. find :math:`i` such
that :math:`E_i < E < E_{i+1}` and calculate the interpolation factor :math:`f`
via :eq:`interpolation-factor`. Then, we intepolate between the minimum and
maximum energies of the outgoing energy distributions corresponding to
:math:`E_i` and :math:`E_{i+1}`:
.. math::
:label: ace-law-1-minmax
E_{min} = E_{i,1} + f ( E_{i+1,1} - E_i ) \\
E_{max} = E_{i,M} + f ( E_{i+1,M} - E_M )
where :math:`E_{min}` and :math:`E_{max}` are the minimum and maximum outgoing
energies of a scaled distribution, :math:`E_{i,j}` is the j-th outgoing energy
corresponding to the incoming energy :math:`E_i`, and :math:`M` is the number of
outgoing energy bins. Next, statistical interpolation is performed to choose
between using the outgoing energy distributions corresponding to energy
:math:`E_i` or :math:`E_{i+1}`. Let :math:`\ell` be the chosen table where
:math:`\ell = i` if :math:`\xi_1 > f` and :math:`\ell = i + 1` otherwise where
:math:`\xi_1` is a random number. Now, we randomly sample an equiprobable
outgoing energy bin :math:`j` and interpolate between successive values on the
outgoing energy distribution:
.. math::
:label: ace-law-1-intermediate
\hat{E} = E_{\ell,j} + \xi_2 (E_{\ell,j+1} - E_{\ell,j})
where :math:`\xi_2` is a random number sampled uniformly on :math:`[0,1)`. Since
this outgoing energy may violate reaction kinematics, we then scale it to the
minimum and maximum energies we calculated earlier to get the final outgoing
energy:
.. math::
:label: ace-law-1-energy
E' = E_{min} + \frac{\hat{E} - E_{\ell,1}}{E_{\ell,M} - E_{\ell,1}}
(E_{max} - E_{min})
ACE Law 3 - Inelastic Level Scattering
++++++++++++++++++++++++++++++++++++++
@ -801,25 +849,35 @@ the unresolved range to get the actual cross sections. Lastly, the total cross
section is calculated as the sum of the elastic, fission, capture, and inelastic
cross sections.
.. [Foderaro] Anthony Foderaro, *The Elements of Neutron Interaction Theory*,
MIT Press, Cambridge, Massachusetts (1971).
----------
References
----------
.. [SIGMA1] Dermett E. Cullen and Charles R. Weisbin, "Exact Doppler Broadening
of Tabulated Cross Sections," *Nucl. Sci. Eng.*, **60**, pp. 199-229 (1976).
.. [Doyas] Richard J. Doyas and Sterrett T. Perkins, "Interpolation of Tabular
Secondary Neutron and Photon Energy Distributions," *Nucl. Sci. Eng.*,
**50**, 390-392 (1972).
.. [Foderaro] Anthony Foderaro, *The Elements of Neutron Interaction Theory*,
MIT Press, Cambridge, Massachusetts (1971). **Note:** Students, faculty, and
staff at MIT can obtian a PDF copy of this book for free from the `MIT
Press`_.
.. [Gelbard] Ely M. Gelbard, "Epithermal Scattering in VIM," FRA-TM-123, Argonne
National Laboratory (1979).
.. [Williams] M. M. R. Williams, *The Slowing Down and Thermalization of
Neutrons*, North-Holland Publishing Co., Amsterdam (1966). This book can be
obtained for free from the OECD_.
.. [Levitt] Leo B. Levitt, "The Probability Table Method for Treating Unresolved
Neutron Resonances in Monte Carlo Calculations," *Nucl. Sci. Eng.*, **49**,
pp. 450-457 (1972).
.. [SIGMA1] Dermett E. Cullen and Charles R. Weisbin, "Exact Doppler Broadening
of Tabulated Cross Sections," *Nucl. Sci. Eng.*, **60**, pp. 199-229 (1976).
.. [Squires] G. L. Squires, *Introduction to the Theory of Thermal Neutron
Scattering*, Cambridge University Press (1978).
.. [Levitt] Leo B. Levitt, "The Probability Table Method for Treating Unresolved
Neutron Resonances in Monte Carlo Calculations," *Nucl. Sci. Eng.*, **49**,
pp. 450-457 (1972).
.. [Williams] M. M. R. Williams, *The Slowing Down and Thermalization of
Neutrons*, North-Holland Publishing Co., Amsterdam (1966). **Note:** This
book can be obtained for free from the OECD_.
.. |sab| replace:: S(:math:`\alpha,\beta`)
@ -836,3 +894,5 @@ cross sections.
.. _MC21: http://www.osti.gov/bridge/servlets/purl/903083-HT5p1o/903083.pdf
.. _Sutton and Brown: http://www.osti.gov/bridge/product.biblio.jsp?osti_id=307911
.. _MIT Press: http://hdl.handle.net/1721.1/1716