Burn-up calculation of the neutronic and safety parameters of thorium-uranium mixed oxide fuel cycle in a Westinghouse small modular reactor

Published: 23 May 2020| Version 1 | DOI: 10.17632/7ppwx856ms.1
Edwin Humphrey Uguru,
Siti Fairus Abdul Sani,
Mayeen Uddin Khandaker,
mohamad hairie rabir,
Julia AbdulKarim,
Daniel Ugadu Onah,
DA Bradley


The datasets added here could be used to reproduce the burn-up calculation of the Neutronic and Safety parameters of thorium-uranium mixed oxide fuel using three fissile enrichment zones against the conventional single enrichment. The is meant to determine the choice of the three fissile enrichment for thorium-based fuel and its performance at long-lasting temperature differentials.


Steps to reproduce

Run a Monte Carlo simulation using MCNPX 2.7 code integrated with CINDER90 burn-up code.


Nuclear Reactor Physics