• [1]

    . A M F. Atomics Industrial Products Group. Safety Analy-sis Report for Tehran Research Reactor. 19662. Nuclear Research Center, Atomic Energy Organization ofIran. Safety Analysis Report for Tehran Research Reactor(TRR). 20023. Harmon C D, Busch R D. Criticality Calculation with MCNP5: A Primer. Los Alamos National Laboratory, 20064. OAK Ridge National Laboratory. Monte Carlo N-Particle Transport Code System (MCNP4C). Los Alamos National Laboratory, 20005. ANSI/ANS-6.4.3. Gamma-Ray Attenuation Coefficient and Buildup Factor for Engineering Materials. American Nuclear Society, 19916. ANSI/ANS-6.1.1. Neutron and Gamma-Ray Fluence-to-Dose Factors. American Nuclear Society, 19917. Chilton A B. Principles of Radiation Shielding. Prentice-Hall, Inc., 10848. Radulescu G. Automated Variance Reduction for MonteCarlo Shielding Analyses with MCNP. University of Texasat Austin, 20039. Kaynia N, Firoozfar N. Water Quality Control for Tehran Research Reactor, TRR-REP-CHEM-05. Nuclear Research Center, Atomic Energy Organization of Iran, 200710. Blanchard M, Wilson P. Characterization of Gamma Ra-diation Fields at the University of Wisconsin Nuclear Reactor Lab - 1MW TRIGA. University of Wisconsin.www.engr.utexas.edu/trtr/agenda/documents/Blanchard-CaF.pdf