Publication | Open Access
Study of an ADS Loaded with Thorium and Reprocessed Fuel
22
Citations
20
References
2012
Year
EngineeringNuclear PhysicsReactor DesignFuel ScienceReactor PhysicsNuclear Reactor DesignChemistryReactor AnalysisMineral ProcessingFuel BreedingFuel RegenerationChemical EngineeringNuclear Fuel EvolutionNuclear MaterialsNuclear ReactorsMaterials ScienceAds LoadedNuclear FuelNeutron SourceChemisorptionAdsorptionNuclear EngineeringNuclear PowerNuclear EnergyNatural SciencesRecyclingChemical Kinetics
Accelerator-driven systems (ADSs) are investigated for long-lived fission product transmutation and fuel regeneration. The aim of this paper is to investigate the nuclear fuel evolution and the neutronic parameters of a lead-cooled accelerator-driven system used for fuel breeding. The fuel used in some fuel rods was<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>T</mml:mtext><mml:mrow><mml:mtext>232</mml:mtext></mml:mrow><mml:msub><mml:mrow><mml:mtext>hO</mml:mtext></mml:mrow><mml:mn>2</mml:mn></mml:msub></mml:mrow></mml:math>for<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>U</mml:mtext><mml:mrow><mml:mtext>233</mml:mtext></mml:mrow></mml:mrow></mml:math>production. In the other fuel rods was used a mixture based upon Pu-MA, removed from PWR-spent fuel, reprocessed by GANEX, and finally spiked with thorium or depleted uranium. The use of reprocessed fuel ensured the use of<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>T</mml:mtext><mml:mrow><mml:mtext>232</mml:mtext></mml:mrow><mml:msub><mml:mrow><mml:mtext>hO</mml:mtext></mml:mrow><mml:mn>2</mml:mn></mml:msub></mml:mrow></mml:math>without the initial requirement of<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>U</mml:mtext><mml:mrow><mml:mtext>233</mml:mtext></mml:mrow></mml:mrow></mml:math>enrichment. In this paper was used the Monte Carlo code MCNPX 2.6.0 that presents the depletion/burnup capability, combining an ADS source and kcode-mode (for criticality calculations). The multiplication factor (<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:msub><mml:mi>k</mml:mi><mml:mrow><mml:mtext>eff</mml:mtext></mml:mrow></mml:msub></mml:mrow></mml:math>) evolution, the neutron energy spectra in the core at BOL, and the nuclear fuel evolution during the burnup were evaluated. The results indicated that the combined use of<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>T</mml:mtext><mml:mrow><mml:mtext>232</mml:mtext></mml:mrow><mml:msub><mml:mrow><mml:mtext>hO</mml:mtext></mml:mrow><mml:mn>2</mml:mn></mml:msub></mml:mrow></mml:math>and reprocessed fuel allowed<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>U</mml:mtext><mml:mrow><mml:mtext>233</mml:mtext></mml:mrow></mml:mrow></mml:math>production without the initial requirement of<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:mtext>U</mml:mtext><mml:mrow><mml:mtext>233</mml:mtext></mml:mrow></mml:mrow></mml:math>enrichment.
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