1. “SCALE: A Modular Code System for Performing Standardized ComputerAnalyses for Licensing Evaluation,” ORNL/TM-2005/39, Version 5, Vols. I, II, and III (Apr. 2005); see also CCC-725, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
2. J. C. WAGNER, “Acceleration of Monte Carlo Shielding Calculations with an Automated Variance Reduction Technique and Parallel Processing,” PhD Dissertation, The Pennsylvania State University (1997).
3. D. WIARDA, M. E. DUNN, D. E. PEPLOW, T. M. MILLER, and H. AKKURT, “Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6,” NUREG/CR-6990 (ORNL/TM-2008/047), Nuclear Regulatory Commission, Oak Ridge National Laboratory (Feb. 2009).
4. Comparison of measured and calculated neutron transmission through steel for a 252Cf source
5. Comparison of measured and calculated neutron transmission through heavy water for 252Cf source placed in the center of 30 cm diameter sphere