1. Briesmeister, J.F., (Ed.), 2000. MCNP—A general Monte Carlo N-particle transport code, Version 4C. LA-13709-M, Los Alamos National Laboratory.
2. Cristy, M., Eckerman, K.F., 1987. Specific absorbed fractions of energy at various ages from internal photon sources. I. Methods, Oak Ridge National Laboratory, ORNL/TM-8381/V1.
3. Shielding design of the treatment room for an accelerator neutron source for BNCT;Evans,1994
4. Shielding design of a treatment room for an accelerator-based epithermal neutron irradiation facility for BNCT;Evans;Health Phys.,1996
5. International Commission on Radiological Protection, 1991. 1990 Recommendations of the International Commission of Radiological Protection, ICRP Publication 60, Pergamon Press, Oxford.