njoy16.tex

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\title{\bf The NJOY Nuclear Data Processing System,\\Version 2016}
%\author{R. E. MacFarlane and A. C. Kahler\\
%  Theoretical Division\\
%  Los Alamos National Laboratory}
\author{\\
  Original Author:  R. E. MacFarlane\\
  Theoretical Division\\
  Los Alamos National Laboratory\\
\\
\\
Contributing Authors\\
D. W. Muir\\
R. M Boicourt\\
A. C. Kahler\\
J. L. Conlin\\
W. Haeck\\
\\
\\
Current Editor:  A. C. Kahler\\
\\
\\
Original Issue:  December 19, 2016\\
\\
\\
Updated for NJOY2016.53
\\}

\date{November 7, 2019}

\makeindex

\includeonly{
    intro,
    njoyx,
    reconx,
    broadx,
    unresx,
    heatx,
    thermx,
    groupx,
    gaminx,
    errorx,
    covx,
    modex,
    dtfx,
    ccccx,
    matxsx,
    resxsx,
    acex,
    powx,
    wimsx,
    plotx,
    viewx,
    mixx,
    purx,
    leapx,
    gaspx,
    mandtx
}

\newcommand{\exx}[1]{{\rm e}^{\textstyle #1}}
\newcommand{\intall}{\int_{-\infty}^\infty}

\raggedbottom
\begin{document}

\maketitle
\abstract{The NJOY Nuclear Data Processing System, version 2016,
is a comprehensive computer code package for producing pointwise
and multigroup cross sections and related quantities from evaluated
nuclear data in the ENDF-4 through ENDF-6 legacy cardimage
formats.  NJOY works with evaluated files for incident neutrons,
photons, and charged particles, producing libraries for a wide
variety of particle transport and reactor analysis codes.}

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%
\begin{center} \textbf{Disclaimer of Liability:} \end{center}
Neither the United States Government nor the Los Alamos
National Security, LLC., nor any of their employees, makes any warranty,
express or implied, including the warranties of merchantability and
fitness for a particular purpose, or assumes any legal liability or
responsibility for the accuracy, completeness, or usefulness of any
information, apparatus, product, or process disclosed, or represents
that its use would not infringe privately owned rights.

\vspace{0.25in}
\begin{center} \textbf{Disclaimer of Endorsement:} \end{center}
Reference herein to any specific commercial products,
process, or service by trade name, trademark, manufacturer, or otherwise,
does not necessarily constitute or imply its endorsement, recommendation,
or favoring by the United States Government or the Los Alamos National
Security, LLC. The views and opinions of authors expressed herein do not
necessarily state or reflect those of the United States Government or
the Los Alamos National Security, LLC., and shall not be used for
advertising or product endorsement purposes.

\vspace{0.25in}
\begin{center} \textbf{Copyright Notice:} \end{center}
Copyright 2016. Los Alamos National Security, LLC. This software was
produced under U.S. Government contract DE-AC52-06NA25396 for
Los Alamos National Laboratory (LANL), which is operated by
Los Alamos National Security, LLC for the U.S. Department of
Energy. The U.S. Government has rights to use, reproduce, and
distribute this software.  NEITHER THE GOVERNMENT NOR LOS ALAMOS
NATIONAL SECURITY, LLC MAKES ANY WARRANTY, EXPRESS OR IMPLIED, OR
ASSUMES ANY LIABILITY FOR THE USE OF THIS SOFTWARE.  If software
is modified to produce derivative works, such modified software
should be clearly marked, so as not to confuse it with the version
available from LANL.

Additionally, redistribution and use in source and binary forms, with
or without modification, are permitted provided that the following
conditions are met:
\begin{enumerate}
\item Redistributions of source code must retain the above copyright
notice, this list of conditions and the following disclaimer.
\item Redistributions in binary form must reproduce the above
copyright notice, this list of conditions and the following disclaimer
in the documentation and/or other materials provided with the
distribution.
\item Neither the name of Los Alamos National Security, LLC, Los
Alamos National Laboratory, LANL, the U.S. Government, nor the
names of its contributors may be used to endorse or promote products
derived from this software without specific prior written permission.
\end{enumerate}
THIS SOFTWARE IS PROVIDED BY LOS ALAMOS NATIONAL SECURITY,
LLC AND CONTRIBUTORS "AS IS" AND ANY EXPRESS OR IMPLIED WARRANTIES,
INCLUDING, BUT NOT LIMITED TO, THE IMPLIED WARRANTIES OF
MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE ARE
DISCLAIMED. IN NO EVENT SHALL LOS ALAMOS NATIONAL SECURITY,
LLC OR CONTRIBUTORS BE LIABLE FOR ANY DIRECT, INDIRECT, INCIDENTAL,
SPECIAL, EXEMPLARY, OR CONSEQUENTIAL DAMAGES (INCLUDING, BUT NOT
LIMITED TO, PROCUREMENT OF SUBSTITUTE GOODS OR SERVICES; LOSS OF
USE, DATA, OR PROFITS; OR BUSINESS INTERRUPTION) HOWEVER CAUSED
AND ON ANY THEORY OF LIABILITY, WHETHER IN CONTRACT, STRICT
LIABILITY, OR TORT (INCLUDING NEGLIGENCE OR OTHERWISE) ARISING IN
ANY WAY OUT OF THE USE OF THIS SOFTWARE, EVEN IF ADVISED OF THE
POSSIBILITY OF SUCH DAMAGE.

\vspace{7.1in}
\begin{center}
\copyright Copyright 2016 Los Alamos National Security,
LLC All Rights Reserved
\end{center}
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\fancyfoot[LO,RE]{NJOY2016}
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%
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% ... which inserts a blank even numbered page, if necessary
\include{intro}
\include{njoyx}
\include{reconx}
\include{broadx}
\include{unresx}
\include{heatx}
\include{thermx}
\include{groupx}
\include{gaminx}
\include{errorx}
\include{covx}
\include{modex}
\include{dtfx}
\include{ccccx}
\include{matxsx}
\include{resxsx}
\include{acex}
\include{powx}
\include{wimsx}
\include{plotx}
\include{viewx}
\include{mixx}
\include{purx}
\include{leapx}
\include{gaspx}
\include{mandtx}

%\section{References}
%comment out so "References" doesn't get a section number in the TOC
\begin{thebibliography}{99}
\begin{singlespace}
\bibitem{NJ1} R. E. MacFarlane and R. M. Boicourt, ``NJOY:  A
  Neutron and Photon Processing System,'' {\it Trans. Am. Nucl.
  Soc.} \underline{22}, 720 (1975).

\bibitem{NJ2} R. E. MacFarlane, D. W. Muir, and R. M. Boicourt,
  ``The NJOY Nuclear Data Processing System, Volume 1:
  User's Manual,'' Los Alamos National Laboratory report
  LA-9303-M, Vol. I (ENDF-324), (May 1982).  R. E. MacFarlane,
  D. W. Muir, and R. M. Boicourt, ``The NJOY Nuclear Data
  Processing System, Volume II: The NJOY, RECONR, BROADR,
  HEATR, and THERMR Modules,'' Los Alamos National Laboratory
  report LA-9303-M, Vol. II (ENDF-324) (May 1982).
  R. E. MacFarlane and D. W. Muir, ``The NJOY Nuclear Data
  Processing System, Volume III: The GROUPR, GAMINR, and
  MODER Modules,'' Los Alamos National Laboratory report
  LA-9303-M, Vol. III (ENDF-324) (October 1987).  D. W. Muir
  and R. E. MacFarlane, ``The NJOY Nuclear Data Processing
  System, Volume IV: The ERRORR and COVR Modules,'' Los Alamos
  National Laboratory report LA-9303-M, Vol. IV (ENDF-324)
  (December 1985).

\bibitem{NJOY91} R. E. MacFarlane and D. W. Muir, ``The NJOY
  Nuclear Data Processing System, Version 91,'' Los Alamos National
  Laboratory report LA-12740-M (1994).

\bibitem{NJ10} R. E. MacFarlane and A. C. Kahler, ``Methods
 for Processing ENDF/B-VII with NJOY," {\it Nuclear Data Sheets},
 {\bf 111}, 2739--2890 (2010).

\bibitem{NJ12} A. C. Kahler, editor, ``The NJOY Nuclear Data
  Processing System, Version 2012,'' Los Alamos National
  Laboratory report LA-UR-12-27079 (2012).

\bibitem{njoytutorial} For an online tutorial on NJOY, see
 \href{http://t2.lanl.gov}{http://t2.lanl.gov}, and follow links
 to the ``Nuclear Information Service (NIS)", ``Training area"
 and ``NJOY" which leads to ``Understanding NJOY,'' Los Alamos
 National Laboratory report LA-UR-00-1538 (March 2000).

\bibitem{ENDF7} M. B. Chadwick {\it et al.}, ``ENDF/B-VII.0:
  Next Generation Evaluated Nuclear Data Library for Nuclear
  Science and Technology,'' {\it Nuclear Data Sheets}, {\bf 107},
  2931--3060 (2006).

\bibitem{ENDF71} M. B. Chadwick {\it et al.}, ``ENDF/B-VII.1 Nuclear
  Data for Science and Technology:  Cross Sections, Covariances,
  Fission Product Yields and Decay Data,'' {\it Nuclear Data Sheets},
  {\bf 112}, 2887--2996 (2011).

\bibitem{ENDF102} A. Trkov, M. Herman and D. A. Brown, Eds., ``ENDF-6
  Formats Manual, Data Formats and Procedures for the Evaluated Nuclear
  Data Files ENDF/B-VI and ENDF/B-VII,'' Brookhaven National Laboratory
  report BNL-90365-2009 Rev.2 (CSEWG Document
  ENDF-102) (October 24, 2012). For the latest version of
  this report, see \href{http://www.nndc.bnl.gov}{http://www.nndc.bnl.gov}
  and take the ``CSEWG'' tab to ``ENDF-6 Formats Manual.''

\bibitem{endftutorial} For an online tutorial on the ENDF formats,
 see \href{http://t2.lanl.gov}{http://t2.lanl.gov}, and follow links
 to the ``Nuclear Information Service (NIS)", ``Training area"
 and ``ENDF" which leads to ``An Introduction to the ENDF Formats,"
 Los Alamos National Laboratory report LA-UR-98-1779 (January 1998).

\bibitem{CCCC4} R. D. O'Dell, ``Standard Interface Files and
  Procedures for Reactor Physics Codes, Version IV,'' Los Alamos
  Scientific Laboratory report LA-6941-MS (September 1977).

\bibitem{TRANSX} R. E. MacFarlane,  ``TRANSX-CTR: A Code for
  Interfacing MATXS Cross-Section Libraries to Nuclear Transport
  Codes for Fusion Systems Analysis,'' Los Alamos National
  Laboratory report LA-9863-MS (February 1984).

\bibitem{ANISN} W. W. Engle, Jr., ``A Users Manual for ANISN,
  A One-Dimensional Discrete Ordinates Transport Code with
  Anisotropic Scattering,'' Oak Ridge Gaseous Diffusion Plant
  Computing Technology Center report K-1693 (1967).

\bibitem{ONEDANT} R. D O'Dell, F. W. Brinkley, Jr.,
  D. R. Marr, and R. E. Alcouffe, ``Revised User's
  Manual for ONEDANT: A Code Package for One-Dimensional,
  Diffusion-Accelerated, Neutral-Particle Transport,''
  Los Alamos National Laboratory report LA-9184-M, Rev.
  (December 1989).

\bibitem{TWODANT} R. E. Alcouffe, F. W. Brinkley, D. R. Marr,
  and R. D. O'Dell, ``User's Guide for TWODANT: A Code Package
  for Two-Dimensional, Diffusion-Accelerated, Neutral-Particle
  Transport,'' Los Alamos National Laboratory report
  LA-10049 Revised (February 1990).

\bibitem{DIF3D} K. L. Derstine, ``DIF3D: A Code to Solve One-,
  Two-, and Three-Dimensional Finite-Difference Diffusion Theory
  Problems,'' Argonne National Laboratory report ANL-82-64
  (April 1984).

\bibitem{PARTISN} R. E. Alcoufe, R. S. Baker, J. A. Dahl, S. A. Turner,
  and R. C. Ward, ``PARTISN: A Time-Dependent, Parallel Neutral Particle
  Transport Code System," Los Alamos National Laboratory report
  LA-UR-05-3925 (Revised May 2005).

\bibitem{MCNP} X-5 Monte Carlo Team, ``MCNP--A General Monte Carlo
  N-Particle Transport Code, Version 5," Los Alamos National
  Laboratory report LA-UR-03-1987 (April 2003).

\bibitem{WIMS} J. R. Askew, F. J. Fayers, and P. B. Kemshell,
  ``A General Description of the Lattice Code WIMS,''
  {\it J. Brit. Nucl. Energy Soc.} \underline{5}, 564 (1966).

\bibitem{webinclude} Userinput information may be found on
 the NJOY homepage, found under the ``Nuclear Information
 Service (NIS)", ``Codes" and ``NJOY" links at
 \href{http://t2.lanl.gov}{http://t2.lanl.gov}.

\bibitem{MINX} C. R. Weisbin, P. D. Soran, R. E. MacFarlane,
  D. R. Harris, R. J. LaBauve, J. S. Hendricks, J. E. White,
  and R. B. Kidman, ``MINX, A Multigroup Interpretation of
  Nuclear X-Sections from ENDF/B,'' Los Alamos Scientific
  Laboratory report LA-6486-MS (ENDF-237) (September 1976).

\bibitem{LAPHAN0} D. J. Dudziak, R. E. Seamon, and D. V. Susco,
  ``LAPHAN0:  A Multigroup Photon-Production Matrix and Source
  Code for ENDF,'' Los Alamos Scientific Laboratory report
  LA-4750-MS (ENDF-156) (January 1972).

\bibitem{GAMLEG} K. D. Lathrop, ``GAMLEG--A FORTRAN Code to
  Produce Multigroup Cross Sections for Photon Transport Calculations,''
  Los Alamos Scientific Laboratory report LA-3267 (April 1965).

\bibitem{DTF} K. D. Lathrop, ``DTF-IV, A FORTRAN Program for
  Solving the Multigroup Transport Equation with Anisotropic
  Scattering,'' Los Alamos Scientific Laboratory report
  LA-3373 (November 1965).

\bibitem{ETOPL} R. J. LaBauve, C. R. Weisbin, R. E. Seamon,
  M. E. Battat, D. R. Harris, P. G. Young, and M. M. Klein,
  ``PENDF: A Library of Nuclear Data for Monte Carlo
  Calculations Derived from Data in the ENDF/B Format,''
  Los Alamos Scientific Laboratory report LA-5687 (October 1974).

\bibitem{RESEND} O. Ozer, Ed. ``Description of the ENDF/B
  Processing Codes and Retrieval Subroutines,'' Brookhaven
  National Laboratory report BNL-50300 (ENDF-11) (June 1971).

\bibitem{SIGMA1} D. E. Cullen, ``Program SIGMA1 (Version 74-1),''
  Lawrence Livermore Laboratory report UCID-16426 (January 1974).

\bibitem{ETOX} R. E. Schenter, J. L. Baker, and R. B. Kidman,
  ``ETOX, A Code to Calculate Group Constants for Nuclear Reactor
  Calculations,'' Battelle Northwest Laboratory report
  BNWL-1002 (1969).

\bibitem{CCCC3} B. M. Carmichael, ``Standard Interface Files and
  Procedures for Reactor Physics Codes, Version III,'' Los Alamos
  Scientific Laboratory report LA-5486-MS (1974).

\bibitem{MACK} M. A. Abdou, C. W. Maynard, and R. Q. Wright,
  ``MACK: A Computer Program to Calculate Neutron Energy Release
  Parameters (Fluence to Kerma Factors) and Multigroup
  Neutron Reaction Cross Sections from Nuclear Data in ENDF
  Format,'' Oak Ridge National Laboratory report ORNL-TM-3994
  (1973).

\bibitem{FLANGE} H. C. Honek and D. R. Finch, ``FLANGE-II
  (Version 71-1), A Code to Process Thermal Neutron Data frp, an
  ENDF/B Tape,'' E. I. DuPont de Nemours and Co. Savannah River
  Laboratory report DP-1278 (1971).

\bibitem{HEXSCAT} Y. D. Naliboff and J. U. Koppel, ``HEXSCAT,
  Coherent Elastic Scattering of Neutrons by Hexagonal Lattices,''
  General Atomic report GA-6026 (1964).

\bibitem{NJ78} R. E. MacFarlane, R. J. Barrett, D. W. Muir, and
  R. M. Boicourt, ``NJOY: A Comprehensive ENDF/B Processing System,''
  in A Review of Multigroup Nuclear Cross-Section Processing,
  Proceedings of a Seminar-Workshop, Oak Ridge, Tennessee,
  March 14-16, 1978,'' Oak Ridge National Laboratory report
  ORNL/RSIC-41 (October 1978).

\bibitem{NJ89} R. E. MacFarlane, ``Introducing NJOY89,'' in
  Proceedings of the Seminar on NJOY and Themis, 20-21 June 1989,
  OECD/NEA Data Bank, Saclay, France (1989).  See also ``Nuclear
  Theory and Application Progress Report, January 1, 1989---April
  1, 1990,'' pp. 21-38, Los Alamos National Laboratory report
  LA-11972-PR (December 1990).

\bibitem{ERRORJ} Go Chiba, ``ERRORJ, A Code to Process Neutron-Nuclide
  Reaction Covariance, Version 2.3,'' JAEA-Data/Code 2007-007, March 2007.

\bibitem{SAMMY} N.M.Larson, ``Updated Users' Guide for SAMMY:
  Multilevel R-Matrix Fits to Neutron Data Using Bayes' Equations,''
  Oak Ridge National Laboratory report ORNL/TM-9179/R8 (October 2008).

\bibitem{MC2} B. J. Toppel, A. L. Rago, and D. M. O'Shea,
  ``MC$^2$, A Code to Calculate Multigroup Cross Sections,''
  Argonne National Laboratory report ANL-7318 (1967).

\bibitem{MC22} H. Henryson II, B. J. Toppel, and C. G. Stenberg,
  ``MC$^2$-2: A Code to Calculate Fast Neutron Spectra and Multigroup
  Cross Sections,'' Argonne National Laboratory report ANL-8144
  (ENDF-239) (1976).

\bibitem{Bondarenko} I. I. Bondarenko, Ed., {\it Group Constants for Nuclear
  Reactor Calculations} (Consultants Bureau, New York, 1964).

\bibitem{Kidman} R. B. Kidman, ``Cross Section Structure Factor
   Interpolation Schemes,'' Hanford Engineering Development
   Laboratory report HEDL-TME-71-40 (1971).

\bibitem{TRANSX2} R. E. MacFarlane, ``TRANSX 2: A Code for Interfacing
   MATXS Cross-Section Libraries to Nuclear Transport Codes,''
   Los Alamos National Laboratory report LA-12312-MS (July 1992).

\bibitem{Muir} D. W. Muir, ``Gamma Rays, Q-Values, and Kerma Factors,''
   Los Alamos Scientific Laboratory report LA-6258-MS (March 1976).

\bibitem{ebal} R. E. MacFarlane, ``Energy Balance of ENDF/B-V,''
   Trans. Am. Nucl. Soc. \underbar{33}, 681 (1979).  See also
   R. E. MacFarlane, ``Energy Balance of ENDF/B-V.2,''
   Minutes of the Cross Section Evaluation Working Group
   (available from the National Nuclear Data Center, Brookhaven
   National Laboratory, Upton, NY) (May 1984).

\bibitem{Gabriel} T. A. Gabriel, J. D. Amburgy, and N. M. Greene,
   ``Radiation-Damage Calculations: Primary Knock-On Atom Spectra,
   Displacement Rates, and Gas Production Rates,''
   {\it Nucl. Sci. Eng.} \underline{61}, 21 (1976).

\bibitem{Doran} D. G. Doran, ``Neutron Displacement Cross Sections for
   Stainless Steel and Tantalum Based on a Linhard Model,'' {\it Nucl. Sci.
   Eng.} \underline{49}, 130 (1972).

\bibitem{Greenwood} L. R. Greenwood and R. K. Smither, ``Displacement
   Damage Calculations with ENDF/B-V,'' in Proceedings of the Advisory Group
   Meeting on Nuclear Data for Radiation Damage Assessment and Reactor
   Safety Aspects, October 12-16, 1981, IAEA, Vienna, Austria (October 1981).

\bibitem{Robinson} M. T. Robinson, in {\it Nuclear Fusion Reactors}
   (British Nuclear Energy Society, London, 1970).

\bibitem{Lindhard} J. Lindhard, V. Nielsen, M. Scharff, and P. V. Thomsen,
   {\it Kgl. Dansk, Vidensk. Selsk, Mat-Fys. Medd.} \underline{33} (1963).

\bibitem{alb} R. E. MacFarlane, D. W. Muir, and F. M. Mann,
   ``Radiation Damage Calculations with NJOY,''
   {\it J. Nucl. Materials} \underline{122} and \underline{123},
   1041 (1984).

\bibitem{advanced} R. E. MacFarlane and D. G. Foster, Jr.,
   ``Advanced Nuclear Data for Radiation Damage Calculations,''
   {\it J. Nucl. Materials} \underline{122} and \underline{123},
   1047 (1984).

\bibitem{old102} R. Kinsey, Ed., ``ENDF-102, Data Formats and Procedures
   for the Evaluated Nuclear Data File, ENDF,'' Brookhaven National
   Laboratory report BNL-NCS-50496 (ENDF-102) 2nd Edition
   (ENDF/B-V) (October 1979).

\bibitem{GAreport} J. U. Koppel and D. H. Houston, ``Reference Manual
   for ENDF Thermal Neutron Scattering Data,'' General Atomic report
   GA-8774 revised and reissued as ENDF-269 by the National Nuclear Data
   Center, Brookhaven National Laboratory (1978).

\bibitem{ref5} G. I. Bell and S. Glasstone, {\it Nuclear Reactor Theory}
  (Van Nostrand Reinhold, New York, 1970).

\bibitem{1DX} R. W. Hardie and W. W. Little, Jr., ``1DX, A One-Dimensional
  Diffusion Code for Generating Effective Nuclear Cross Sections,''
  Battelle Northwest Laboratory report BNWL-954 (1969).

\bibitem{ref9} R. E. MacFarlane, ``ENDF/B-IV and -V Cross Sections for Thermal
  Power Reactor Analysis,'' in Proc. Intl. Conf. of Nuclear Cross Sections
  for Technology, Knoxville, TN (October 22-26 1979), National Bureau of
  Standards Publication 594 (September 1980).

\bibitem{ref10} G. I. Bell, G. E. Hansen, and H. A. Sandmeier, ``Multitable
  Treatments of Anisotropic Scattering in S$_{\rm N}$ Multigroup
  Transport Calculations,'' Nucl. Sci. Eng. \underbar{28}, 376 (1967).

\bibitem{ref13}  M. Abramowitz and I. Stegun, {\it Handbook of Mathematical
  Functions} (Dover Publications, New York, 1965).

\bibitem{ref14}  D. G. Madland, ``New Fission Neutron Spectrum
  Representation for ENDF,'' Los Alamos National Laboratory
  report LA-9285-MS (ENDF-321) (April 1982).

\bibitem{km} C. Kalbach and F. M. Mann, ``Phenomenology of Continuum
   Angular Distributions. I. Systematics and Parameterization,''
   Phys. Rev. C. \underline{23}, 112 (1981).

\bibitem{k86} C. Kalbach, ``Systematics of Continuum Angular Distributions:
  Extensions to Higher Energies,''  {\it Phys. Rev. C.}
  \underline{37}, 2350 (1988).

\bibitem{GNASH} P. G. Young and E. D. Arthur, ``GNASH: A Preequilibrium
  Statistical Nuclear Model Code for Calculation of Cross Sections and
  Emission Spectra,''  Los Alamos Scientific Laboratory report LA-6947 (1977).

\bibitem{powr} R. E. MacFarlane, ``ENDF/B-V Cross-Section
  Library for Reactor Cell Analysis,'' Electric Power Research
  Institute report EPRI NP-3418 (February 1984).

\bibitem{LIBIV} R. B. Kidman and R. E. MacFarlane, ``LIB-IV, A Library
  of Group Constants for Nuclear Reactor Calculations,'' Los Alamos
  Scientific Laboratory report LA-6260-MS (1976).

\bibitem{one} G. Lehner, ``Reaction Rates and Energy Spectra
  for Nuclear Reactions in High Energy Plasmas,'' {\it Z. Physik}
  {\bf 232}, 174 (1970).

\bibitem{two} D. E. Nagle, W. E. Quinn, W. B. Riesenfeld,
  and W. Leland, ``Ion Temperature in Scylla, as Determined from the
  Reaction D(d,p)T,'' {\it Phys. Rev. Letters} {\bf 3}, 318 (1959).

\bibitem{three} N. Jarmie and J. D. Seagrave (Eds.),
  ``Charged Particle Cross Sections,'' Los Alamos Scientific
  Laboratory report LA-2014 (1956).

\bibitem{four} D. W. Muir, ``Sensitivity of Neutron Multigroup
  Cross Sections to Thermal Broadening of the Fusion Peak,''
  Proc. 1st Topical Meeting on the Technology of Controlled
  Nuclear Fusion, San Diego, Calif., April 1974,
  CONF-740402-P2, p.166 (1975).

\bibitem{HUGO}  R. W. Roussin, J. R. Knight, J. H. Hubbell, and R. J. Howerton,
  ``Description of the DLC-99/HUGO Package of Photon Interaction Data in
  ENDF/B-V Format,'' Oak Ridge National Laboratory report ORNL/RSIC-46
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\bibitem{data} These data were obtained from the paper of Keinert
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\end{thebibliography}

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