Mixed-oxide fuel strategies in an integral pressurized water reactor

The integral pressurized water reactor (iPWR) will play an important role in nuclear energy development considering its outstanding safety features. To achieve high proliferation resistance, extended fuel cycles have been proposed. Other important issues to achieve nuclear energy long-term sustainab...

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Veröffentlicht in:Progress in nuclear energy (New series) 2021-09, Vol.139, p.103844, Article 103844
Hauptverfasser: Betancourt, Mariana C., García Hernández, Carlos R., Dominguez, Dany S., Rojas Mazaira, Leorlen Y., Brayner, Carlos A., Rosales García, Jesús A., Iglesias, Susana M.
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Sprache:eng
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Zusammenfassung:The integral pressurized water reactor (iPWR) will play an important role in nuclear energy development considering its outstanding safety features. To achieve high proliferation resistance, extended fuel cycles have been proposed. Other important issues to achieve nuclear energy long-term sustainability are the proper use of its fuel sources and the improvement of nuclear waste management. Therefore, fuels based on oxides mixture have been successfully used in several countries. Also, Thorium-based fuel incorporation is a current challenge for the new advanced reactor designs. This paper compared different fuel compositions using recycled Plutonium and Uranium in a conceptual reactor of the type iPWR. The use of Thorium as fertile material is presented as well. The presented study considers a standard fuel cycle with slightly enriched Uranium (below 5%) as reference. One-third of the conceptual iPWR’s core is loaded with MOX fuel assemblies and the other two-thirds with conventional UO2. These proposed fuel cycles are compared with the standard full-UO2 cycle, regarding the behavior of main safety parameters, fuel depletion, and waste production. The studied fuel compositions reached a fuel cycle length of 4 years, approximately. The results for the core parameters show that using MOX and Thorium-based fuels in iPWR fulfills the safety constraints. •Five MOX fuel strategies were analyzed in an extended fuel cycle in the proposed iPWR core.•One-third of the core is loaded with MOX fuel assemblies and the other two-thirds with conventional UO2.•The lowest maximum value of radial power peak factor was obtained for the MOX fuel assemblies at the core center.•Thorium-based fuel compositions reduces the initial mass of Pu239 considerably.•The results showed that the main safety parameters obtained are not a constraint for the core safety.
ISSN:0149-1970
1878-4224
DOI:10.1016/j.pnucene.2021.103844