Decrease of the economically accessible uranium resources and the inherent proliferation resistance
of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic
parameters during different operational situations is of key importance for the safe operation of nuclear reactors.
In the present research, thorium oxide fuel burn-up calculations for a demonstrative model of a heavy water-
-cooled reactor have been performed using MCNPX 2.6 code. Neutronic parameters for three different thorium
fuel matrices loaded separately in the modelled thermal core have been investigated. 233U, 235U and 239Pu isotopes
have been used as fi ssile element in the thorium oxide fuel, separately. Burn-up of three different fuels has been
calculated at 1 MW constant power. 135X and 149Sm concentration variations have been studied in the modelled
core during 165 days burn-up. Burn-up of thorium oxide enriched with 233U resulted in the least 149Sm and 135Xe
productions and net fi ssile production of 233U after 165 days. The negative fuel, coolant and void reactivity of the
used fuel assures safe operation of the modelled thermal core containing (233U-Th) O2 matrix. Furthermore, utilisation
of thorium breeder fuel demonstrates several advantages, such as good neutronic economy, 233U production
and less production of long-lived α emitter high radiotoxic wastes in biological internal exposure point of view.
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