The NJOY Nuclear Data Processing System, Volume 1:User's Manual

Computing Center at Lawrence Livermore National Laboratory, CDC-7600 (SCOPE) at
the Brookhaven National Laboratory, IBM-360/195 (MTD/FTX) at Argonne National
Laboratory, UNIVAC-1108 at the Hanford Engineering Development Laboratory of
Westinghouse, and the IBM-360/195 at the Oak Ridge National Laboratory.
VII. ACKNOWLEDGEMENTS
The IBM conversion was performed by R. Q. Wright and J. E. Lucius at Oak
Ridge National Laboratory and D. Cambra and C. Stenberg at Argonne National
Laboratory. The UNIVAC conversion was performed by F. W. Mann at the Hanford
Engineering and Development Laboratory. Thanks are also due to Odelli Ozer of
the Electric Power Research Institute for help with the RESEND code and the de-
sign of the thermal processing capability; to D. E. Cullen of the Lawrence
Livermore National Laboratory and J. Hancock of Los Alamos for their work on
the Doppler-broadening module; to P. G. Young for help with the heating calcula-
tion; to R. E. Seamen, P. D. Soran, W. B. Wilson, D. George, R. B. Kidman, and
L. Stewart (all of Los Alamos) for help with testing and validation; to R. J.
Barrett of Los Alamos for his extensive work on the CCCC and MATXS systems; and
to R. J. LaBauve of Los Alamos, D. R. Harris and M. Becker of Rensselaer Poly-
technic Institute, and C. R. Weisbin of Oak Ridge National Laboratory, for moral
support, ideas, and constructive criticism.
REFERENCES
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R. E. t4acFarlane and R. M. Boicourt, “NJOY: A Neutron and photon
Cross Section Processing System,” Trans. Am. Nuc1. SOC. ~, 720 (1975).
R. E. MacFarlane, D. W. Muir, and R. J. Barrett, “Advanced Nuclear Data
Processing Methods for the Fusion Power Program,” Trans. Am. Nucl. SOC.
23, 16 (1976).
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, p. 25 (October 1978).
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).
K. D. Lathro~. “DTF-IV, A FORTRAN Program for Solving the Multigroup
Transport Equation with- Anisotropic Scattering,” LOS Alamos Scientific
Laboratory report LA-3373 (November 1965).
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