1. J. F. Briesmeister, ed., “MCNP–A General Monte Carlo Code for Neutron and Photon Transport, Version 3A,” Los Alamos National Laboratory, LA-7396-M Rev. 2 (1986).
2. R. Kinsey, “Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF,” Brookhaven National Laboratory, BNL-NCS-50496 (ENDF 102) 2nd Ed. (ENDF/B-V) (Oct. 1979).
3. R. J. Howerton, D. E. Cullen, R. C. Haight, M. H. MacGregor, S. T. Perkins, and E. F. Plechaty, “The LLL Evaluated Nuclear Data Library (ENDL): Evaluation Techniques, Reaction Index, and Descriptions of Individual Reactions,” Lawrence Livermore National Laboratory, UCRL-50400 Vol. 15, Part A (Sept. 1975).
4. M. A. Gardner and R. J. Howerton, “ACTL: Evaluated Neutron Activation Cross Section Library - Evaluation Techniques and Reaction Index,” Lawrence Livermore National Laboratory, UCRL-50400 Vol. 18 (Oct. 1978).
5. E. D. Arthur and P. G. Young, “Evaluated Neutron-Induced Cross-Sections for 54,56.Fe to 40 MeV,” Los Alamos Scientific Laboratory, LA-8626-MS (ENDF-304) (Dec. 1980 ).