Prediction of neutron energy spectrum in a typical MTR type research reactor using Monte Carlo simulations

Abstract

In previous work, determination of the neutron energy spectrum in a typical pool type Material Test research Reactor (MTR) was discussed. Solution of the neutron spectrum adjustment problem, which adjusts a theoretically calculated spectrum to a set of experimentally measured reaction rates, was also analyzed. The calculated spectrum was obtained through modelling the reactor core and the surroundings in three dimensions using the deterministic code CITATION. In this work, the same core configuration was modelled in three dimensions using the Monte Carlo code, MCNP5. The calculated spectrum by MCNP is compared to that calculated by CITATION. Both calculated spectra by CITATION and MCNP were also compared as input information in the experimental determination of the neutron spectrum through the use of experimentally measured reaction rates and the adjustment code MSITER. The good agreement between the calculated and adjusted spectra indicates that the MCNP approach can be used as pre-information in the experimental determination of the neutron spectrum as well as for the prediction of neutron spectrum at other locations.