Calculation of the effective multiplication factor, neutron flux and power distribution for ETRR-2 Egyptian Second research reactor using MCNP4C2 code
published by Damascus University
in 2012
in
and research's language is
العربية
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Abstract in English
The MCNP4C2 Monte Carlo code was used to model the Egyptian Second
research reactor in this paper, to calculate the effective multiplication factor
keff, distribution of the thermal and fast neutron fluxes and power in reactor
core with two type of fuels: standard and mixed. The values of the keff were
1.21842 and 1.05272, the maximum thermal flux were 2.975x10+14 and
3.352x10+14 n/cm2s, and the maximum fast flux was 2.950x10+14 and 2.389x10+14
n/cm2s for standard and mixed fuels respectively. The results showed good
agreements with previous results available in the literature.
References used
H. Böck and M. Villa. (2001). “Survey Of Research Reactors” Prepared for the IAEA course on "safety, Management and utilization of Research Reactors" tislava-vienna. March 5-30-2001
Oak Ridge National Laboratory. (2000). “Rsicc Compyter Code Collection MCNP4C” contributed by: Los Alamos National Laboratory Los Alamos, New Mexico
Khamis I. Kattaab K. Suleman I. and Ghazi N. (2006). “Neutronic design of a 22 MW MTR type nuclear research reactor” Syrian Atomic Energy Commission