References
- M. VALENZANO, Booz/Allen/Hamilton, Personal Communication (Mar. 2005).
- N. B. McLEOD, “The Radiological Capacity of Transport Casks Loaded in a 2-Region Non-Uniform Pattern,” Proc. 2nd Ann. Int. Conf. High Level Radioactive Waste Management, May 1991.
- N. B. McLEOD, “Reducing Environmental Impacts Through Non-Uniform Loading of Casks,” Proc. 7th Ann. Int. Conf. High Level Radioactive Waste Management, May 1996.
- J. M. CUTA, U. P. JENQUIN, and M. A. McKINNON, “Evaluation of Effect of Fuel Assembly Loading Patterns on Thermal and Shielding Performance of a Spent Fuel Storage/Transportation Cask,” PNNL-13583, Pacific Northwest National Laboratories (Nov. 2001).
- I. C. GAULD and O. W. HERMAN, “SAS2: A Coupled One-Dimensional Depletion and Shielding Analysis Module,” ORNL/TM-2005/39, Oak Ridge National Laboratory (Apr. 2005).
- “MCNP—A General Monte Carlo N-Particle Transport Code, Version 5,” LA-UR-03-1987, S. M. GIRARD and J. B. SHINN, Eds., Los Alamos National Laboratory (2004).
- “Package and Transportation of Radioactive Materials,” Title 10, Part 71, Code of Federal Regulations.
- Nuclear Fuel Data Form RW-859, U.S. Department of Energy (data as of Dec. 31, 2002).
- H. B. Robinson Final Safety Analysis Report, Rev. 18, Chap. 4. 10. E. REDMOND, Holtec International, Personal Communication (Apr. 2005).
- A. LUKSIC, “Spent Fuel Assembly Hardware: Characterization and 10CFR61 Classification forWaste Disposal,” PNL-6906-Vol. 1, Pacific Northwest Laboratory (June 1989).
- T. A. PARISH, “Effects of Burnup Distributions on the Reactivity of Spent Fuel,” Proc. 5th Ann. Int. Conf. High Level Radioactive Waste Management, Vol. 2, p. 745 (1994).
- J. H. SALING and A. W. FENTIMAN, Radioactive Waste Management, pp. 339–340, Taylor and Francis (2002).
- S. AGACE, Holtec International, Personal Communication (Jan. 2008).