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
Contributors:
Edwin Humphrey UGURU, Siti Fairus Abdul Sani, Mayeen Uddin Khandaker, Mohamad Hairie Rabir, Julia Abdul Karim, Daniel Ugadu Onah, David BradleyDescription
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.
Files
Steps to reproduce
Run a Monte Carlo simulation using MCNPX 2.7 code integrated with CINDER90 burn-up code.
Categories
Nuclear Reactor Physics