analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the candu reactor
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ID: 148644
2017
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Abstract
This study presents the determination of fuel rejuvenation times in a D-T
fusion breeder reactor fuelled with a mixture of natUO2 and ThO2 for
multi-reuse of nuclear fuels in CANDU-37 reactors. To determine the effect of
thorium on the fuel enrichment and rejuvenation times, neutronic analyses are
performed by increasing the percentage of ThO2 in the fuel mixture from 10 to
35. The time-dependent neutronic calculations are carried out in three
stages. In the first stage, which is the fuel enrichment or rejuvenation
process in the fusion breeder reactor, the subcritical calculations of the
fusion breeder reactor fuelled with the fuel mixtures are performed by using
the MCNPX 2.7/CINDER under a fusion neutron wall loading of 1 MWm-2,
corresponding to neutron flux of 4.444•1013 cm-2s-1 (energy of every fusion
neutron is 14.1 MeV). In the second stage, which is the thermal reactor
analysis, the fuel rods enriched at the end of the first stage are placed in
the CANDU-37 reactor, and the critical calculations of this reactor are
performed by using MCNPX 2.7 and MONTEBURNS codes separately. The numerical
results show that the neutronic values obtained from both codes are very near
each other. The third stage is the two-year cooling process of CANDU spent
fuels. The values obtained by numerical calculations show that this fusion
breeder reactor is self-sufficient in terms of tritium and has a high
performance in terms of energy multiplication as well as fuel rejuvenation
and thorium utilization.
| Reference Key |
gizem2017nuclearanalysis
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|---|---|
| Authors | ;Bakir Gizem;Yapici Huseyin |
| Journal | postepy higieny i medycyny doswiadczalnej (online) |
| Year | 2017 |
| DOI |
10.2298/NTRP1703193B
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| URL | |
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