References
- “MCNP—Monte Carlo Neutron and Photon Transport Code,” RSIC-CCC 200, ORNL, Oak Ridge National Laboratory (1989); cross-section data retrieved from ENDF/B-IV in ACE format, BMCCS2 (neutrons) and MCPLIB (photons)
- D. K. MOHAPATRA et al., “Flux Measurements and Power Calibration in Kamini Reactor,” IGC-201,Indira Gandhi Center for Atomic Research (1998).
- G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, Van Nostrand Reinhold Company, New York (1970).
- P. MOHANAKRISHNAN, “LWR Assembly Code SMAXY and its IGCAR Version,” RPD/CPOS/21,Indira Gandhi Center for Atomic Research (1990).
- J. C. WAGNER et al., “MCNP Criticality Safety Benchmark Problems,” LA-12415, Los Alamos National Laboratory (1992).
- K. V. SUBBAIAH et al., “Comparison of MCNP and KENO: Criticality Safety Benchmark Problems,” IGC-189, Indira Gandhi Center for Atomic Research (1997).
- K. V. SUBBAIAH et al., “Application of Variance Reduction Techniques of Monte Carlo Method to Deep Penetration Shielding Problems,” Conf. Proc. Radiation Shielding and Protection (RASP-96), Indira Gandhi Centre for Atomic Research (1996).
- A. B. CHILTON et al., Principles of Radiation Shielding, Prentice-Hall, Englewood Cliffs, New Jersey.
- “Flux to Dose Conversion Factors,” ANSI/ANS-6.1.11977, American National Standards Institute/American Nuclear Society (1977).
- K. V. SUBBAIAH and K. K. RAWAT, “Shielding Calculations of South Beam Port of KAMINI Reactor,” IGC-203, Indira Gandhi Center for Atomic Research (1998).
- K. VISHWAPRASAD, Private Communication (health physics report).