1. Briesmeister, J. F. (1993) MCNP — A general Monte Carlo N-particle transport code, LA-12625-M.
2. Radioactivity of 51Cr in stainless steel collected from residences in the JCO neighborhood;Endo;Journal of Environmental Radioactivity,2000
3. International Commission on Radiological Protection (ICRP) 1987. Data for use in protection against external radiation, publication 51, Oxford: Pergamon Press.
4. Calculation of the amount of neutrons and activation; calculation of the amount of produced fission products; a report on the measurement of radioactive contamination around the accident site;Imanaka;Journal of Environmental Radioactivity,2000