1. Bengston, J., , “2DXY Two Dimensional, Cartesian Coordinate Sn Transport Calculation,” U. S. AEC Research and Development Report, AGNTM-392, 061961.
2. Duane, B. H., “Neutron and Photon Transport Plane-Cylinder-Sphere (GE-ANPD) Program S Variational Optimum Formulation,” General Electric Company XOC-9-118, 1959.
3. Lathrop, K. D., “DTF-IV, A Fortran-IV Program for Solving the Multigroup Transport Equation with Anisotropic Scattering,” LA-3373, Los Alamos Scientific Laboratory, 1965 .
4. Little, W. W. Jr., and Hardie, R. W., “2DB, A Two-Dimensional Diffusion-Burnup Code for Fast Reactor Analysis,” BNWL-640, Pacific Northwest Laboratory, 1968 .
5. McElroy, W. N., Berg, S., Crockett, T. B., and Hawkins, R. G., “A Computer-Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation,” AFWL-TR-67-41, Vol. I–IV, Air Force Weapons Laboratory, 1967 .