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Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor
Author(s) -
Uguru Edwin H.,
Abdul Sani Siti F.,
Khandaker Mayeen U.,
Rabir Mohamad H.,
Karim Julia A.,
Onah Daniel U.,
Bradley David A.
Publication year - 2020
Publication title -
international journal of energy research
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.808
H-Index - 95
eISSN - 1099-114X
pISSN - 0363-907X
DOI - 10.1002/er.6000
Subject(s) - fissile material , nuclear engineering , mox fuel , thorium fuel cycle , enriched uranium , spent nuclear fuel , uranium , environmental science , thorium , nuclear fuel cycle , materials science , waste management , fuel cycle , nuclear physics , engineering , neutron , physics , metallurgy
Summary Thorium fuel is presently a globally known future nuclear fuel alternative, having good neutronic, physical and chemical properties in addition to its spent nuclear fuel characteristic proliferation resistance. This research focused on the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle, utilising three fissile enrichment zones, a departure from the conventional single enrichment. The aim was to determine the range of three fissile zones adequate for thorium‐uranium fuel cycle; investigating the performance efficiency of the fuel neutronic and inherent safety parameters in response to temperature differentials, which determines the viability of the fuel and core composition. Use was made of the MCNPX 2.7 code integrated with the CINDER90 fuel depletion code for steady‐state and burn‐up calculations. The k eff , moderator temperature coefficient (MTC) and fuel temperature coefficient (FTC) of reactivity are affected by the range of fissile enrichment and fuel temperature which decreased with their respective increases. The MTC for all the moderator temperatures was within 0 to −40 pcm/K design value for UO 2 fuel. Similarly, the FTC was within −3.5 to −1 pcm/K design value for all the fuel temperatures except after 2000 days, where a positive reactivity feedback was introduced. At ~86 MWd/kgHM single discharge burn‐up, the result shows that ~90% of the initial fissile load was utilised for energy production at the normal reactor operating temperature (600 K) with a slight reduction at higher fuel temperature. The total fissile inventory ratio (FIR), 233 U/kg‐ 232 Th and 239 Pu/kg‐ 238 U inventory ratios were significantly large and increased with burn‐up. It is remarkable that the FIR and the 233 U/kg‐ 232 Th inventory ratio did not reach conversion equilibrium until exit burn‐up. The large percentage fuel utilisation supports the advantage of fissile enrichment zoning in a thermal nuclear reactor core, making the chosen novel three fissile enrichment zones for thorium‐uranium fuel cycle reliable.