2005•KerntechnikRequires access

Neutronic calculations for the new fuel configuration of the ETRR-1 research reactor

Moustafa Aziz

Abstract

Abstract Neutronic calculations were performed for the new loading configuration of the ETRR-1 research reactor. The MCNP three dimensions Monte Carlo code and the two dimensions CITATION code are used to model the reactor. The power and thermal flux distributions in the reactor core are calculated. The power peak factor and the effect of control rod insertion on both flux and power profiles in the reactor core are determined and analyzed. The partial and total control rods worth are calculated. It was found that the difference between MCNP and CITATION in power distributions is 4 to 8 % and for thermal flux ranges between 3 to 14 %.

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Key concepts: Nuclear engineering, Control rod, Research reactor, Nuclear reactor core, Rod, Flux (metallurgy), Monte Carlo method, Core (optical fiber)