1. MCNP—A General Monte Carlo N-Particle Transport Code (Version C);Briesmeister,1997
2. China Institute of Atomic Energy, 1993. Safety Analysis Report of the MNSR Reactor, China.
3. IAEA, 1970. Neutron fluence measurements. Technical Report No. 107, IAEA, Vienna.
4. Khamis, I., Khattab, K., Hainoun, A., 1999. Set of Experiments in Nuclear Engineering Associated with the Syrian Miniature Neutron Source Reactor, Syria.
5. Measurement of the fast neutron flux in the MNSR inner irradiation site;Khattab;Applied Radiation and Isotopes,2007